Friday, June 19, 2009

A Superb Record of Nuclear Safety


Although Chernobyl blemished the image of nuclear energy, the accident's positive legacy is an even stronger system of nuclear safety worldwide. In 1989, the nuclear industry established the World Association of Nuclear Operators (WANO) to foster a global nuclear safety culture. Through private-sector diplomacy, WANO has built a transnational network of technical exchange that includes all countries with nuclear power. Today every nuclear power reactor in the world is part of the WANO system of operational peer review. The aim of WANO's peer-review system standards set by the UN's International Atomic Energy Agency (IAEA).

Advances in safety practice are unmistakable. At most plants worldwide, reportable safety-related 'events' are now near zero. National and international insurance laws assign responsibility to nuclear plant operators. In the U.S. for example, reactor operators share in a 'pooled' private insurance system that has never cost taxpayers a penny.

Today, nuclear power plants have a superb safety record - both for plant workers and the public. In the transport of nuclear material, highly engineered containers - capable of withstanding enormous impact - are the industrial norm. More than 20,000 containers of spent fuel and high-level waste have been shipped safely over a total distance exceeding 30 million kilometres. During the transport of these and other

radioactive substances - whether for research, medicine or nuclear - there had never been a harmful radioactive release.

Facts on Radiation

Radiation is release naturally from the ground and atmosphere in all places on Earth. This 'natural background' radiation, which varies considerable from region to region, is part of the environment to which all human beings are conditioned. Like many things, radiation can be both beneficial and harmful. Large doses are dangerous. Abundant evidence indicates that small doses are harmless.

The radiation produced within the core of nuclear reactors is similar to natural radiation but more intense. At nuclear power plants, protective shielding isolates this radiation, allowing millions of people to live in safety nearby. Typically, the radiation people receive comes 90% from nature and 10% from medical exposures. Radiation exposure from nuclear power is negligible.
source: world-nuclear.org

Radioisotopes in Medicine


* Nuclear medicine uses radiation to provide diagnostic information about the functioning of a
person's specific organs, or to treat them. Diagnostic procedures are now routine.
* Radiotherapy can be used to treat some medical conditions, especially cancer, using radiation to
weaken or destroy particular targeted cells.
* Tens of millions of nuclear medicine procedures are performed each year, and demand for
radioisotopes is increasing rapidly.

Nuclear Medicine

This is a branch of medicine that uses radiation to provide information about the functioning of a person's specific organs or to treat disease. In most cases, the information is used by physicians to make a quick, accurate diagnosis of the patient's illness. The thyroid, bones, heart, liver and many other organs can be easily imaged, and disorders in their function revealed. In some cases radiation can be used to treat diseased organs, or tumours. Five Nobel Laureates have been intimately involved with the use of radioactive tracers in medicine.

Over 10,000 hospitals worldwide use radioisotopes in medicine, and about 90% of the procedures are for diagnosis. The most common radioisotope used in diagnosis is technetium-99, with some 30 million procedures per year, accounting for 80% of all nuclear medicine procedures worldwide.

In developed countries (26% of world population) the frequency of diagnostic nuclear medicine is 1.9% per year, and the frequency of therapy with radioisotopes is about one tenth of this. In the USA there are some 18 million nuclear medicine procedures per year among 305 million people, and in Europe about 10 million among 500 million people. In Australia there are about 560,000 per year among 21 million people, 470,000 of these using reactor isotopes. The use of radiopharmaceuticals in diagnosis is growing at over 10% per year.

Nuclear medicine was developed in the 1950s by physicians with an endocrine emphasis, initially using iodine-131 to diagnose and then treat thyroid disease. In recent years specialists have also come from radiology, as dual CT/PET procedures have become established.

Computed X-ray tomography (CT) scans and nuclear medicine contribute 36% of the total radiation exposure and 75% of the medical exposure to the US population, according to a US National Council on Radiation Protection & Measurements report in 2009. The report showed that Americans’ average total yearly radiation exposure had increased from 3.6 millisievert to 6.2 mSv per year since the early 1980s, due to medical-related procedures. (Industrial radiation exposure, including that from nuclear power plants, is less than 0.1% of overall public radiation exposure.)

Diagnosis

Diagnostic techniques in nuclear medicine use radioactive tracers which emit gamma rays from within the body. These tracers are generally short-lived isotopes linked to chemical compounds which permit specific physiological processes to be scrutinised. They can be given by injection, inhalation or orally. The first type are where single photons are detected by a gamma camera which can view organs from many different angles. The camera builds up an image from the points from which radiation is emitted; this image is enhanced by a computer and viewed by a physician on a monitor for indications of abnormal conditions.

A more recent development is Positron Emission Tomography (PET) which is a more precise and sophisticated technique using isotopes produced in a cyclotron. A positron-emitting radionuclide is introduced, usually by injection, and accumulates in the target tissue. As it decays it emits a positron, which promptly combines with a nearby electron resulting in the simultaneous emission of two identifiable gamma rays in opposite directions. These are detected by a PET camera and give very precise indication of their origin. PET's most important clinical role is in oncology, with fluorine-18 as the tracer, since it has proven to be the most accurate non-invasive method of detecting and evaluating most cancers. It is also well used in cardiac and brain imaging.

New procedures combine PET with computed X-ray tomography (CT) scans to give co-registration of the two images (PETCT), enabling 30% better diagnosis than with traditional gamma camera alone. It is a very powerful and significant tool which provides unique information on a wide variety of diseases from dementia to cardiovascular disease and cancer (oncology).

Positioning of the radiation source within the body makes the fundamental difference between nuclear medicine imaging and other imaging techniques such as x-rays. Gamma imaging by either method described provides a view of the position and concentration of the radioisotope within the body. Organ malfunction can be indicated if the isotope is either partially taken up in the organ (cold spot), or taken up in excess (hot spot). If a series of images is taken over a period of time, an unusual pattern or rate of isotope movement could indicate malfunction in the organ.

A distinct advantage of nuclear imaging over x-ray techniques is that both bone and soft tissue can be imaged very successfully. This has led to its common use in developed countries where the probability of anyone having such a test is about one in two and rising.

The mean effective dose is 4.6 mSv per diagnostic procedure.

Positron Emission Tomography (PET)

Radionuclide therapy (RNT)

Rapidly dividing cells are particularly sensitive to damage by radiation. For this reason, some cancerous growths can be controlled or eliminated by irradiating the area containing the growth. External irradiation (sometimes called teletherapy) can be carried out using a gamma beam from a radioactive cobalt-60 source, though in developed countries the much more versatile linear accelerators are now being utilised as a high-energy x-ray source (gamma and x-rays are much the same).

Internal radionuclide therapy is by administering or planting a small radiation source, usually a gamma or beta emitter, in the target area. Short-range radiotherapy is known as brachytherapy, and this is becoming the main means of treatment. Iodine-131 is commonly used to treat thyroid cancer, probably the most successful kind of cancer treatment. It is also used to treat non-malignant thyroid disorders. Iridium-192 implants are used especially in the head and breast. They are produced in wire form and are introduced through a catheter to the target area. After administering the correct dose, the implant wire is removed to shielded storage. This brachytherapy (short-range) procedure gives less overall radiation to the body, is more localised to the target tumour and is cost effective.

Treating leukaemia may involve a bone marrow transplant, in which case the defective bone marrow will first be killed off with a massive (and otherwise lethal) dose of radiation before being replaced with healthy bone marrow from a donor.

Many therapeutic procedures are palliative, usually to relieve pain. For instance, strontium-89 and (increasingly) samarium 153 are used for the relief of cancer-induced bone pain. Rhenium-186 is a newer product for this.

A new field is Targeted Alpha Therapy (TAT), especially for the control of dispersed cancers. The short range of very energetic alpha emissions in tissue means that a large fraction of that radiative energy goes into the targeted cancer cells, once a carrier has taken the alpha-emitting radionuclide to exactly the right place. Laboratory studies are encouraging and clinical trials for leukaemia, cystic glioma and melanoma are under way.

An experimental development of this is Boron Neutron Capture Therapy using boron-10 which concentrates in malignant brain tumours. The patient is then irradiated with thermal neutrons which are strongly absorbed by the boron, producing high-energy alpha particles which kill the cancer. This requires the patient to be brought to a nuclear reactor, rather than the radioisotopes being taken to the patient.

Radionuclide therapy has progressively become successful in treating persistent disease and doing so with low toxic side-effects. With any therapeutic procedure the aim is to confine the radiation to well-defined target volumes of the patient. The doses per therapeutic procedure are typically 20-60 Gy.

Biochemical Analysis

It is very easy to detect the presence or absence of some radioactive materials even when they exist in very low concentrations. Radioisotopes can therefore be used to label molecules of biological samples in vitro (out of the body). Pathologists have devised hundreds of tests to determine the constituents of blood, serum, urine, hormones, antigens and many drugs by means of associated radioisotopes. These procedures are known as radioimmuno-assays and, although the biochemistry is complex, kits manufactured for laboratory use are very easy to use and give accurate results. In Europe some 15 million of these in vitro analyses are undertaken each year.

Diagnostic Radiopharmaceuticals

Every organ in our bodies acts differently from a chemical point of view. Doctors and chemists have identified a number of chemicals which are absorbed by specific organs. The thyroid, for example, takes up iodine, the brain consumes quantities of glucose, and so on. With this knowledge, radiopharmacists are able to attach various radioisotopes to biologically active substances. Once a radioactive form of one of these substances enters the body, it is incorporated into the normal biological processes and excreted in the usual ways.

Diagnostic radiopharmaceuticals can be used to examine blood flow to the brain, functioning of the liver, lungs, heart or kidneys, to assess bone growth, and to confirm other diagnostic procedures. Another important use is to predict the effects of surgery and assess changes since treatment.

The amount of the radiopharmaceutical given to a patient is just sufficient to obtain the required information before its decay. The radiation dose received is medically insignificant. The patient experiences no discomfort during the test and after a short time there is no trace that the test was ever done. The non-invasive nature of this technology, together with the ability to observe an organ functioning from outside the body, makes this technique a powerful diagnostic tool.

A radioisotope used for diagnosis must emit gamma rays of sufficient energy to escape from the body and it must have a half-life short enough for it to decay away soon after imaging is completed.

The radioisotope most widely used in medicine is technetium-99m, employed in some 80% of all nuclear medicine procedures - 70,000 every day. It is an isotope of the artificially-produced element technetium and it has almost ideal characteristics for a nuclear medicine scan. These are:

* It has a half-life of six hours which is long enough to examine metabolic processes yet short enough to minimise the radiation dose to the patient.
* Technetium-99m decays by a process called "isomeric"; which emits gamma rays and low energy electrons. Since there is no high energy beta emission the radiation dose to the patient is low.
* The low energy gamma rays it emits easily escape the human body and are accurately detected by a gamma camera. Once again the radiation dose to the patient is minimised.
* The chemistry of technetium is so versatile it can form tracers by being incorporated into a range of biologically-active substances to ensure that it concentrates in the tissue or organ of interest.

Its logistics also favour its use. Technetium generators, a lead pot enclosing a glass tube containing the radioisotope, are supplied to hospitals from the nuclear reactor where the isotopes are made. They contain molybdenum-99, with a half-life of 66 hours, which progressively decays to technetium-99. The Tc-99 is washed out of the lead pot by saline solution when it is required. After two weeks or less the generator is returned for recharging.

A similar generator system is used to produce rubidium-82 for PET imaging from strontium-82 - which has a half-life of 25 days.

Myocardial Perfusion Imaging (MPI) uses thallium-201 chloride or technetium-99m and is important for detection and prognosis of coronary artery disease.

For PET imaging, the main radiopharmaceutical is Fluoro-deoxy glucose (FDG) incorporating F-18 - with a half-life of just under two hours, as a tracer. The FDG is readily incorporated into the cell without being broken down, and is a good indicator of cell metabolism.

In diagnostic medicine, there is a strong trend to using more cyclotron-produced isotopes such as F-18 as PET and CT/PET become more widely available. However, the procedure needs to be undertaken within two hours reach of a cyclotron.

Therapeutic Radiopharmaceuticals

For some medical conditions, it is useful to destroy or weaken malfunctioning cells using radiation. The radioisotope that generates the radiation can be localised in the required organ in the same way it is used for diagnosis - through a radioactive element following its usual biological path, or through the element being attached to a suitable biological compound. In most cases, it is beta radiation which causes the destruction of the damaged cells. This is radionuclide therapy (RNT) or radiotherapy. Short-range radiotherapy is known as brachytherapy, and this is becoming the main means of treatment.

Although radiotherapy is less common than diagnostic use of radioactive material in medicine, it is nevertheless widespread, important and growing. An ideal therapeutic radioisotope is a strong beta emitter with just enough gamma to enable imaging, eg lutetium-177. This is prepared from ytterbium-176 which is irradiated to become Yb-177 which decays rapidly to Lu-177. Yttrium-90 is used for treatment of cancer, particularly non-Hodgkin's lymphoma, and its more widespread use is envisaged, including for arthritis treatment. Lu-177 and Y-90 are becoming the main RNT agents.

Iodine-131 and phosphorus-32 are also used for therapy. Iodine-131 is used to treat the thyroid for cancers and other abnormal conditions such as hyperthyroidism (over-active thyroid). In a disease called Polycythemia vera, an excess of red blood cells is produced in the bone marrow. Phosphorus-32 is used to control this excess.

A new and still experimental procedure uses boron-10, which concentrates in the tumour. The patient is then irradiated with neutrons which are strongly absorbed by the boron, to produce high-energy alpha particles which kill the cancer.

For targeted alpha therapy (TAT), actinium-225 is readily available now, from which the daughter Bi-213 can be obtained (via 3 alpha decays) to label targeting molecules.

Considerable medical research is being conducted worldwide into the use of radionuclides attached to highly specific biological chemicals such as immunoglobulin molecules (monoclonal antibodies). The eventual tagging of these cells with a therapeutic dose of radiation may lead to the regression - or even cure - of some diseases.

Radioisotope Poisons

In 2006 Britain witnessed the apparent murder of one of its newer citizens, a former Russian intelligence official, by poisoning with radioactive polonium. His death was slow and excruciating.

Polonium has about 26 isotopes, all of which are radioactive. Webelements periodic table says that it is 250 billion times more toxic than hydrocyanic acid. It is readily soluble in weak acid. (It was the first element discovered by Marie Curie, in 1898, and named after her native Poland. Her daughter Irene was contaminated with polonium in a laboratory accident and died of leukemia at the age of 59.)

Polonium-210 is the penultimate decay product of U-238, before it alpha decays to become stable lead. It results from the beta decay of Pb-210 (in the U-238 decay series) to Bi-210 which rapidly beta decays to Po-210. This gives rise to its occurrence in nature, where uranium is ubiquitous. However, because of its short (138 day) half life, very little Po-210 would be found in uranium ore or mill tailings (Webelements suggests 0.1 mg/tonne). Po-210 levels in soil would be even less, but it is concentrated in tobacco and traces of it can be found in smokers' urine.

Po-210 can also be made by neutron irradiation of Bi-209, and that is most likely source of any significant quantity. Russia has used Po-210 as a heat source in short-life spacecraft and lunar rovers. It also operates reactors using lead-bismuth cooling, which becomes contaminated with Po-210 due to neutron bombardment.

Because its half-life is so short, a gram of Po-210 is about 5000 times as radioactive as a gram of radium - which sets the standard of activity. But at 138 days its half life is long enough for it to be manufactured, transported and administered before its loses its potency. It would not put the carrier at much risk, since alpha radiation is only really a hazard inside the body - a layer of skin is protection. About 10 micrograms (2 GBq) was said to have been used, administered in a cup of tea (it would be warm due to the decay).

However, simply dosing someone with polonium might not have much effect if it simply went in one end and out the other in a day or two without being absorbed from the gut. It would probably need to be complexed on to an organic carrier which would enter the bloodstream and take it to vital organs where it would stay. (This is what happens with targeted alpha therapy (TAT) using very low levels of alpha-active radioisotopes: the carriers take them to dispersed cancerous tissues where they are needed.)

In Mr Litvinenko's case the intense alpha radiation was reportedly in vital organs and sufficient to destroy them over three weeks. It was apparently over one hundred times the dose used in TAT for cancer treatment and the Po-210 is much longer-lived than isotopes used for TAT. It could have been attached to something as simple as a sugar.

Supplies of radioisotopes

Medical radioisotopes made in nuclear reactors are sourced from relatively few reactors, including:

- NRU at Chalk River in Canada (supplied via MDS Nordion)

- HFR at Petten in Netherlands (supplied via IRE and Covidien/Tyco)

- BR-2 at Mol in Belgium (supplied via IRE and Covidien/Tyco)

- Osiris & Orphee at Saclay in France (supplied via IRE)

- FRJ-2/ FRM-2 at Julich in Germany (supplied via IRE)

- LWR-15 at Rez in Czech Republic

- HFETR at Chengdu in China

- Safari in South Africa (supplied from NTP)

- Opal in Australia (supplied from ANSTO)

Of fission radioisotopes, 40% of Mo-99 (for Tc-99m) comes from MDS Nordion, 25% from Covidien (formerly Tyco), 20% from IRE and 10% from NTP. For I-131, 75% is from IRE, 25% from NTP.

Mo-99 is mostly prepared by fission of U-235 targets in a nuclear research reactor. As of 2008, most was produced using high-enriched uranium. The targets are then processed to separate the Mo-99 and also I-131.

A number of incidents in 2008 pointed up shortcomings and unreliability in the supply of isotopes, particular technetium. Some 95% of the world's supply of this comes from only five reactors, all of them over 40 years old. A major and increasing supply shortfall of Tc-99 is forecast from 2010. Australia's Opal reactor has the capacity to produce half the world supply of it, but a much larger Mo production facility would be required. Also the processing and distribution of isotopes is complex and constrained, which can be critical when the isotopes concerned are short-lived. A need for increased production capacity and more reliable distribution is evident.

In January 2009 Babcock & Wilcox (B&W) announced an agreement with international isotope supplier Covidien to produce Mo-99 sufficient for half of US demand, if a new process involving an innovative reactor and separation technology is successful. They plan to use Aqueous Homogeneous Reactor (AHR) technology with low-enriched uranium in small 100-200 kW units. A single production facility could have four such reactors. B&W and Covidien expect a five-year lead time to first production. (LEU is dissolved in acid then brought to criticality in a 200-litre vessel. As fission proceeds the solution is circulated through an extraction facility to remove the fission products with Mo-99 and then back into the reactor vessel, which is at low temperature and pressure.)

Wastes

The use of radioisotopes for medical diagnosis and treatments results in the generation of mainly Low-Level Waste (LLW). This waste includes paper, rags, tools, clothing and filters, which contain small amounts of mostly short-lived radioactivity. These types of waste often undergo decay storage for periods of months to a few years before being disposed of at urban land-fill sites.

When radiography sources have decayed to a point where they are no longer emitting enough penetrating radiation for use in treatments, they are considered as radioactive waste. Sources such as Co-60 are treated as short-lived Intermediate-Level wastes (ILW). Other sources such as Radium-226, used in cancer therapy, will however require long-term storage and geological disposal as ILW, as a result of their higher level of long-lived radioactivity.

Isotopes used in Medicine

Many radioisotopes are made in nuclear reactors, some in cyclotrons. Generally neutron-rich ones and those resulting from nuclear fission need to be made in reactors, neutron-depleted ones are made in cyclotrons. There are about 40 activation product radioisotopes and five fission product ones made in reactors.

Reactor Radioisotopes (half-life indicated)

Bismuth-213 (46 min): Used for targeted alpha therapy (TAT), especially cancers.

Chromium-51 (28 d): Used to label red blood cells and quantify gastro-intestinal protein loss.

Cobalt-60 (5.27 yr): Formerly used for external beam radiotherapy.

Dysprosium-165 (2 h): Used as an aggregated hydroxide for synovectomy treatment of arthritis.

Erbium-169 (9.4 d): Use for relieving arthritis pain in synovial joints.

Holmium-166 (26 h): Being developed for diagnosis and treatment of liver tumours.

Iodine-125 (60 d): Used in cancer brachytherapy (prostate and brain), also diagnostically to evaluate the filtration rate of kidneys and to diagnose deep vein thrombosis in the leg. It is also widely used in radioimmuno-assays to show the presence of hormones in tiny quantities.

Iodine-131 (8 d)*: Widely used in treating thyroid cancer and in imaging the thyroid; also in diagnosis of abnormal liver function, renal (kidney) blood flow and urinary tract obstruction. A strong gamma emitter, but used for beta therapy.

Iridium-192 (74 d): Supplied in wire form for use as an internal radiotherapy source for cancer treatment (used then removed).

Iron-59 (46 d): Used in studies of iron metabolism in the spleen.

Lutetium-177 (6.7 d): Lu-177 is increasingly important as it emits just enough gamma for imaging while the beta radiation does the therapy on small (eg endocrine) tumours. Its half-life is long enough to allow sophisticated preparation for use. It is usually produced by neutron activation of natural or enriched lutetium-176 targets.

Molybdenum-99 (66 h)*: Used as the 'parent' in a generator to produce technetium-99m.

Palladium-103 (17 d): Used to make brachytherapy permanent implant seeds for early stage prostate cancer.

Phosphorus-32 (14 d): Used in the treatment of polycythemia vera (excess red blood cells). Beta emitter.

Potassium-42 (12 h): Used for the determination of exchangeable potassium in coronary blood flow.

Rhenium-186 (3.8 d): Used for pain relief in bone cancer. Beta emitter with weak gamma for imaging.

Rhenium-188 (17 h): Used to beta irradiate coronary arteries from an angioplasty balloon.

Samarium-153 (47 h): Sm-153 is very effective in relieving the pain of secondary cancers lodged in the bone, sold as Quadramet. Also very effective for prostate and breast cancer. Beta emitter.

Selenium-75 (120 d): Used in the form of seleno-methionine to study the production of digestive enzymes.

Sodium-24 (15 h): For studies of electrolytes within the body.

Strontium-89 (50 d)*: Very effective in reducing the pain of prostate and bone cancer. Beta emitter.

Technetium-99m (6 h): Used in to image the skeleton and heart muscle in particular, but also for brain, thyroid, lungs (perfusion and ventilation), liver, spleen, kidney (structure and filtration rate), gall bladder, bone marrow, salivary and lacrimal glands, heart blood pool, infection and numerous specialised medical studies. Produced from Mo-99 in a generator.

Xenon-133 (5 d)*: Used for pulmonary (lung) ventilation studies.

Ytterbium-169 (32 d): Used for cerebrospinal fluid studies in the brain.

Ytterbium-177 (1.9 h): Progenitor of Lu-177.

Yttrium-90 (64 h)*: Used for cancer brachytherapy and as silicate colloid for the relieving the pain of arthritis in larger synovial joints. Pure beta emitter and of growing significance in therapy.

Radioisotopes of caesium, gold and ruthenium are also used in brachytherapy.

* fission product

Cyclotron Radioisotopes

Carbon-11, Nitrogen-13, Oxygen-15, Fluorine-18: These are positron emitters used in PET for studying brain physiology and pathology, in particular for localising epileptic focus, and in dementia, psychiatry and neuropharmacology studies. They also have a significant role in cardiology. F-18 in FDG (fluorodeoxyglucose) has become very important in detection of cancers and the monitoring of progress in their treatment, using PET.

Cobalt-57 (272 d): Used as a marker to estimate organ size and for in-vitro diagnostic kits.

Copper-64 (13 h): Used to study genetic diseases affecting copper metabolism, such as Wilson's and Menke's diseases, and for PET imaging of tumours, and therapy.

Copper-67 (2.6 d): Beta emitter, used in therapy.

Fluorine-18 as FLT (fluorothymidine), F-miso (fluoromisonidazole), 18F-choline: tracer.

Gallium-67 (78 h): Used for tumour imaging and localisation of inflammatory lesions (infections).

Gallium-68 (68 min): Positron emitter used in PET and PET-CT units. Derived from germanium-68 in a generator.

Germanium-68 (271 d): Used as the 'parent' in a generator to produce Ga-68.

Indium-111 (2.8 d): Used for specialist diagnostic studies, eg brain studies, infection and colon transit studies.

Iodine-123 (13 h): Increasingly used for diagnosis of thyroid function, it is a gamma emitter without the beta radiation of I-131.

Iodine-124: tracer.

Krypton-81m (13 sec) from Rubidium-81 (4.6 h): Kr-81m gas can yield functional images of pulmonary ventilation, e.g. in asthmatic patients, and for the early diagnosis of lung diseases and function.

Rubidium-82 (1.26 min): Convenient PET agent in myocardial perfusion imaging.

Strontium-82 (25 d): Used as the 'parent' in a generator to produce Rb-82.

Thallium-201 (73 h): Used for diagnosis of coronary artery disease other heart conditions such as heart muscle death and for location of low-grade lymphomas.

What are radioisotopes?

Many of the chemical elements have a number of isotopes. The isotopes of an element have the same number of protons in their atoms (atomic number) but different masses due to different numbers of neutrons. In an atom in the neutral state, the number of external electrons also equals the atomic number. These electrons determine the chemistry of the atom. The atomic mass is the sum of the protons and neutrons. There are 82 stable elements and about 275 stable isotopes of these elements.

When a combination of neutrons and protons, which does not already exist in nature, is produced artificially, the atom will be unstable and is called a radioactive isotope or radioisotope. There are also a number of unstable natural isotopes arising from the decay of primordial uranium and thorium. Overall there are some 1800 radioisotopes.

At present there are up to 200 radioisotopes used on a regular basis, and most must be produced artificially.

Radioisotopes can be manufactured in several ways. The most common is by neutron activation in a nuclear reactor. This involves the capture of a neutron by the nucleus of an atom resulting in an excess of neutrons (neutron rich). Some radioisotopes are manufactured in a cyclotron in which protons are introduced to the nucleus resulting in a deficiency of neutrons (proton rich).

The nucleus of a radioisotope usually becomes stable by emitting an alpha and/or beta particle (or positron). These particles may be accompanied by the emission of energy in the form of electromagnetic radiation known as gamma rays. This process is known as radioactive decay.

Radioactive products which are used in medicine are referred to as radiopharmaceuticals.

Appendix to Information Paper 55

New reactor needed for medical imaging - why cyclotrons cannot do the job

Article from May 1999 edition Australasian Science Magazine

(June 1999)

Rex Boyd defends the decision to commission a new nuclear reactor.

It is claimed by opponents of the nuclear industry that Australia's demand for medical radioisotopes can be met by cyclotrons. The truth is that any number of cyclotrons will never replace Australia's need for a reactor.

Australia has two cyclotrons, which use high voltages and electrical fields to accelerate hydrogen atoms through a vacuum chamber. When they collide with a target substance they produce radioactivity.

As a general rule, it is more difficult to make a radioisotope in a cyclotron than in a reactor. Cyclotron reactions are less productive and less predictable than nuclear reactions performed in a reactor.

The cyclotron produces neutron-deficient radioisotopes whereas the reactor produces neutron-rich radioisotopes. Thus the reactor and the cyclotron complement each other in satisfying society's need for a full range of radioisotopes; rarely one acts as a substitute for the other.

A few radioisotopes are exceptions to this rule and can be produced by either facility. One is technetium-99m, currently used in 85% of medical applications. The discovery that technetium-99m can be produced in a cyclotron does not imply that the need for a reactor is disappearing.

The half-life of technetium-99m is 6 hours. This means that this radioisotope must be produced and distributed on a daily basis.

However, when technetium-99m is produced in a reactor it proceeds through a precursor radioisotope, molybdenum-99, which has a half-life of 66 hours. Thus the weekly production of molybdenum-99 generators can meet all the technetium-99m needs of Australian hospitals.

In contrast the cyclotron does not produce molybdenum-99; instead it produces technetium-99m directly. Therefore a network of cyclotrons situated across Australia would be needed to make daily deliveries of technetium-99m to the nation's hospitals. This is one reason why none of the many powerful cyclotrons around the world are used for the manufacture of technetium-99m.

Reliance on cyclotrons for our most frequently used medical isotope would have a serious negative impact on the practice of nuclear medicine. The rapid decay of technetium-99m would limit the number of patients treated in any one day and would preclude the use of nuclear medicine techniques in out-of-hours emergency situations when stocks would be exhausted. Appointments would be subject to technetium-99m availability and patient waiting lists would lengthen.

Economic factors would also militate against cyclotron-produced technetium-99m. The raw materials for reactor production are cheap (a few dollars per kilogram) and readily available, whereas the starting material for the cyclotron-method is a rare form of molybdenum that must be enriched to high levels of isotopic purity (>99%), is not commercially available and would cost millions of dollars per kilogram.

Traces of other molybdenum isotopes in the raw materials can reduce the purity of the technetium-99m. A series of competing nuclear reactions produces undesirable longer-lived technetium radioisotopes, particularly technetium-96, that can accumulate during the day. The level of these impurities may exceed the legal limit and degrade the quality of the scanned image.

Other technetium radioisotopes would expose patients to higher radiation doses. Only 0.1% technetium-96 is necessary before radiation exposure of patients is doubled. Hence before cyclotron-produced technetium-99m could be used, certain regulations governing radiopharmaceutical quality would need changing.

The cyclotron production of technetium-99m is technically feasible but undesirable for all of these reasons.

The frontiers of nuclear medicine now extend beyond the diagnosis of disease with technetium-99m. Other short-lived radioisotopes are being introduced into nuclear medicine with the capability of reducing the pain associated with cancer. Australia must have its own reactor if its community is to have access to these radioisotopes and reap the benefits of the latest advances.
source: world-nuclear.org

Plans For New Reactors Worldwide


  • Nuclear power capacity worldwide is increasing steadily but not dramatically, with over 40 reactors under construction in 12 countries.
  • Most reactors on order or planned are in the Asian region, though plans are firming for new units in Europe, the USA and Russia.
  • Significant further capacity is being created by plant upgrading.
  • Plant life extension programs are maintaining capacity, in USA particularly.

Today there are some 439 nuclear power reactors operating in 30 countries plus Taiwan, with a combined capacity of over 370 GWe. In 2007 these provided 2608 billion kWh, about 15% of the world's electricity.

Over 40 power reactors are currently being constructed in 11 countries (see Table below), notably China, South Korea, Japan and Russia.

The International Atomic Energy Agency has significantly increased its projection of world nuclear generating capacity. It now anticipates at least 70 new plants in the next 15 years, making 470 to 750 GWe in place in 2030 - very much more than projected in 2000 and 27% to 103% more than actually operating in 2008. OECD estimates range up to 680 GWe in 2030. The change is based on specific plans and actions in a number of countries, including China, India, Russia, Finland and France, coupled with the changed outlook due to the Kyoto Protocol. This would give nuclear power a 17% share in electricity production in 2020. The fastest growth is in Asia.

It is noteworthy that in the 1980s, 218 power reactors started up, an average of one every 17 days. These included 47 in USA, 42 in France and 18 in Japan. The average power was 923.5 MWe. So it is not hard to imagine a similar number being commissioned in a decade after about 2015. But with China and India getting up to speed with nuclear energy and a world energy demand double the 1980 level in 2015, a realistic estimate of what is possible might be the equivalent of one 1000 MWe unit worldwide every 5 days.

See also Nuclear Renaissance paper for the factors driving the increase in nuclear power capacity, and also WNA's Nuclear Century Outlook.

Increased Capacity

Increased nuclear capacity in some countries is resulting from the uprating of existing plants. This is a highly cost-effective way of bringing on new capacity.

Numerous power reactors in USA, Belgium, Sweden and Germany, for example, have had their generating capacity increased. In Switzerland, the capacity of its five reactors has been increased by 12.3%. In the USA, the Nuclear Regulatory Commission has approved 124 uprates totalling some 5600 MWe since 1977, a few of them "extended uprates" of up to 20%.

Spain has a program to add 810 MWe (11%) to its nuclear capacity through upgrading its nine reactors by up to 13%. For instance, the Almarez nuclear plant is being boosted by more than 5% at a cost of US$ 50 million. Some 519 MWe of the increase is already in place.

Finland Finland has boosted the capacity of the Olkiluoto plant by 29% to 1700 MWe. This plant started with two 660 MWe Swedish BWRs commissioned in 1978 and 1980. It is now licensed to operate to 2018. The Loviisa plant, with two VVER-440 (PWR) reactors, has been uprated by 90 MWe (10%).

Sweden is uprating Forsmark plant by 13% (410 MWe) over 2008-10 at a cost of EUR 225 million, and Oskarshamn-3 by 21% to 1450 MWe at a cost of EUR 180 million.

Nuclear Plant Construction

Most reactors currently planned are in the Asian region, with fast-growing economies and rapidly-rising electricity demand.

Some 16 countries with existing nuclear power programs (Argentina, Brazil, Bulgaria, Canada, France, Russia, China, India, Pakistan, Japan, Romania, Slovakia, South Korea, South Africa, Ukraine, USA) have plans to build new power reactors (beyond those now under construction).

In all, over 100 power reactors with a total net capacity of almost 120,000 MWe are planned and over 250 more are proposed. Rising gas prices and greenhouse constraints on coal have combined to put nuclear power back on the agenda for projected new capacity in both Europe and North America.

In the USA there are proposals for over twenty new reactors and the first 17 combined construction and operating licences for these have been applied for. All are for late third-generation plants, and a further proposal is for two ABWR units.

In Canada there are plans to build up to 3500 MWe of new capacity in Ontario, and proposals for similar capacity in Alberta and one large reactor in New Brunswick.

In Finland, construction is now under way on a fifth, very large reactor which will come on line in 2011 and plans a re firming for another large one to follow it.

France is building a similar 1600 MWe unit at Flamanville, for operation from 2012, and a second is to follow it.

Romania's second power reactor istarted up in 2007, and plans are being implemented for two further Canadian units.

Slovakia is completing two 470 MWe units at Mochovce, to operate from 2011-12.

Bulgaria is about to start building two 1000 MWe Russian reactors at Belene.

In Russia, six large reactors are under active construction and due for completion by 2012, one being a large fast neutron reactor. Seven further reactors are then planned to replace some existing plants, and by 2015 ten new reactors totalling at least 9.8 GWe should be operating. Further reactors are planned to add new capacity by 2020. This will increase the country's present 21.7 GWe nuclear power capacity to 50 GWe about 2020. In addition about 5 GW of nuclear thermal capacity is planned. A small floating power plant is expected to be completed by 2011 and another by 2020.

Poland is planning some nuclear power capacity but initially is likely to join a joint project in Lithuania, with Estonia and Latvia.

Nuclear power will continue to play a major role in the future electricity supply mix in both South Korea and Japan.

South Korea plans to bring a further eight reactors into operation by the year 2015, giving total new capacity of 9200 MWe. Following them are planned Shin-Kori-1 & 2 and Wolsong-5 & 6, to be improved OPR-1000 designs. Then come Shin-Kori-3 & 4 and Shin-Ulchin 1&2, the first of the Advanced PWRs of 1400 MWe, to be in operation by 2016. These APR-1400 designs have evolved from a US design which has US NRC design certification, and have been known as the Korean Next-Generation Reactor.

Japan has two reactors under construction and another ready to start building. It also has plans and, in most cases, designated sites and announced timetables for a further 10 power reactors, totalling over 13,000 MWe which are expected to come on line 2012-18.

In China, now with eleven operating reactors on the mainland, CNNC is well into the next phase of its nuclear power program. The second of two Russian 1000 MWe PWRs at Tianwan in Jiangsu province was grid connected in May 2007.

China NNC and Guangdong NPC have six more indigenous reactors under construction at Lingdong, Qinshan, Hongyanhe and Ningde. Ten more are due to start construction by July 2010 at these sites plus Yangjiang. Four large Western third-generation ones are due to start construction at Sanmen and Haiyang, with two more at Taishan. China aims at least to quadruple its nuclear capacity from that operating and under construction by 2020. The Shidaowan high temperature gas-cooled reactor will start construction in 2009 at Rongcheng , Shandong province.

On Taiwan, Taipower is building two advanced BWRs at Lungmen.

India has six reactors under construction and expected to be completed by 2010. This includes two large Russian reactors and a large prototype fast breeder reactor as part of its strategy to develop a fuel cycle which can utilise thorium. Further units are planned. Ten further units are planned, and plans for more - including western and Russian designs - are taking shape following the lifting of trade restrictions.

Pakistan has a second 300 MWe reactor under construction at Chasma, financed by China. There are plans for more Chinese power reactors.

In Kazakhstan, a joint venture with Russia's Atomstroyexport envisages development and marketing of innovative small and medium-sized reactors, starting with a 300 MWe Russian design as baseline for Kazakh units.

In Iran nuclear power plant construction was suspended in 1979 but in 1995 Iran signed an agreement with Russia to complete a 1000 MWe PWR at Bushehr. Construction is well advanced.

The Turkish government plans to have three nuclear power plants total 4500 MWe operating by 2012-15, a US$ 10.5 billion investment.

Indonesia plans to start constructing a 2000 MWe nuclear power station in 2010.

Vietnam is also considering its first nuclear power venture, to be commissioned by 2017.

Fuller details of all the above contries curently without nuclear power are in country papers or the paper on Emerging Nuclear Energy Countries.

Plant Life Extension

Most nuclear power plants originally had a nominal design lifetime of up to 40 years, but engineering assessments of many plants over the last decade has established that many can operate longer. In the USA nearly 50 reactors have been granted licence renewals which extend their operating lives from the original 40 out to 60 years, and operators of most others are expected to apply for similar extensions. In Japan, plant lifetimes up to 70 years re envisaged.

When the oldest commercial nuclear power stations in the world, Calder Hall and Chapelcross in the UK, were built in the 1950s they were very conservatively engineered, though it was assumed that they would have a useful lifetime of only 20-25 years. They were then authorised to operate for 50 years but due to economic factors closed earlier. Most other Magnox plants are licensed for 40-year lifetimes.

The Russian government in 2000 extended the operating lives of the country's 12 oldest reactors from their original 30 years, for 15 years.

The technical and economic feasibility of replacing major reactor components, such as steam generators in PWRs and pressure tubes in CANDU heavy water reactors, has been demonstrated. The possibilities of component replacement and licence renewals extending the lifetimes of existing plants are very attractive to utilities, especially in view of the public acceptance difficulties involved in constructing replacement nuclear capacity.

On the other hand, economic, regulatory and political considerations have led to the premature closure of some power reactors, particularly in the United States, where reactor numbers have fell from 110 to 104, and in eastern Europe.

Table:

Power reactors under construction, or almost so

Start Operation*
REACTOR TYPE MWe (net)





2009
India, NPCIL
Rawatbhata 5
PHWR
202
2009
India, NPCIL
Kaiga 4
PHWR
202
2009 India, NPCIL
Kudankulam 1

PWR

950

2009 India, NPCIL
Rawatbhata 6
PHWR
202
2009 Iran, AEOI
Bushehr 1
PWR
950
2009 Russia, Energoatom
Volgodonsk 2
PWR
950
2009 Japan, Hokkaido
Tomari 3
PWR
912





2010 India, NPCIL

Kudankalam 2

PWR

950

2010 Canada, Bruce Power Bruce A1 PHWR 769
2010 Canada, Bruce Power
Bruce A2
PHWR
769
2010 Korea, KHNP
Shin Kori 1
PWR
1000
2010 China, CGNPC
Lingao 3
PWR
1080
2010 Argentina, CNEA
Atucha 2
PHWR
692
2010 Russia, Energoatom
Severodvinsk
PWR x 2
70





2011 India, NPCIL
Kalpakkam
FBR
470
2011 Taiwan Power
Lungmen 1
ABWR
1300
2011 Russia, Energoatom
Kalinin 4
PWR
950
2011 Korea, KHNP
Shin Kori 2
PWR
1000
2011 China, CNNC
Qinshan 6
PWR
650
2011 China, CGNPC
Lingao 4
PWR
1080
2011 Pakistan, PAEC
Chashma 2
PWR
300





2012 Finland, TVO

Olkiluoto 3

PWR

1600

2012 China, CNNC
Qinshan 7
PWR
650
2012 Taiwan Power Lungmen 2
ABWR 1300
2012 Korea, KHNP
Shin Wolsong 1
PWR
1000
2012 France, EdF
Flamanville 3
PWR
1630
2012 Russia, Energoatom
Beloyarsk 4
FBR
750
2012 Japan, Chugoku
Shimane 3
PWR
1375
2012 Russia, Energoatom
Novovoronezh 6
PWR
1070
2012 Slovakia, SE
Mochovce 3
PWR
440
2012 China, CGNPC
Hongyanhe 1
PWR
1080
2012 China, CGNPC
Ningde 1
PWR
1080





2013 China, CNNC
Sanmen 1
PWR
1100
2013 China, CGNPC
Ningde 2
PWR
1080
2013 Krea, KHNP

Shin Wolsong 2

PWR

1000

2013 Russia, Energoatom
Leningrad 5
PWR
1070
2013 Russia, Energoatom
Novovoronezh 7
PWR
1070
2013 Russia, Energoatom

Rostov/ Volgodonsk 3

PWR

1070

2013 Korea, KHNP
Shin Kori 3
PWR
1350
2013 China, CGNPC
Yangjiang 1
PWR
1080
2013 China, CGNPC

Taishan 1

PWR

1700

2013 China, CNNC

Fangjiashan 1

PWR

1000

2013 China, CNNC

Fuqing 1

PWR

1000

2013 Slovakia, SE
Mochovce 4
PWR
440





2014 China, CGNPC Hongyanhe 2 PWR 1080
2014 China , CNNC
Sanmen 2
PWR
1100
2014 China , CPI
Haiyang 1
PWR
1100
2014 China , CGNPC
Ningde 3
PWR
1080
2014 China , CGNPC
Hongyanhe 3
PWR
1080
2014 China, CNNC

Fangjiashan 2

PWR

1000

2014 China, CNNC

Fuqing 2

PWR

!000

2014 China, China Huaneng Shidaowan HTR 200
2014 Korea, KHNP
Shin-Kori 4
PWR
1350
2014 Japan, Tepco Fukishima I-7 ABWR 1350
2014 Japan, EPDC/J Power

Ohma

ABWR

1350

2014 Bulgaria, NEK

Belene 1

PWR

1000

2014 Russia , Energoatom
Leningrad 6
PWR
1200
2014 Russia , Energoatom
Rostov/ Volgodonsk 4
PWR
1200





2015 Japan , Tepco
Fukishima I-8
ABWR
1080
2015 China , CGNPC Yangjiang 2 PWR 1080
2015 China , CGNPC Taishan 2
PWR 1700
2015 China , CPI Haiyang 2
PWR 1100
2015 Romania, SNN

Cernavoda 3

PHWR

655

2015 Korea, KHNP
Shin-Ulchin 1 PWR 1350
2015 Russia, Energoatom Seversk 1 PWR 1200
2015 Russia, Energoatom Baltic 1
PWR 1200
2015 Russia, Energoatom Tver 1
PWR 1200
2015 Russia, Energoatom Leningrad 7 PWR 1200
2015 Japan, Chugoku Kaminoseki 1 ABWR 1373
2015 Japan , Tepco
Higashidori 1
ABWR
1080

* Latest announced year of proposed commercial operation.

The World Nuclear Power Reactor table gives a fuller and (for current year) possibly more up to date overview of world reactor status.

Some further power reactors planned

Start
operation
Start
construction

Reactor Type MWe
(each)






2016
2011
Bulgaria, NEK
Belene 2
PWR
1000
2018
?
Japan, Tepco
Higashidori 2 (Tepco)
ABWR
1320
2016-17
2010
Japan, JAPC
Tsuruga 3 & 4
APWR
1500
2018
?
Japan, Chugoku
Kaminoseki 2
ABWR
1373
2016

Korea, KHNP
Shin-Ulchin 2
APR-1400
1350
2017

Slovenia, NEK
Krsko 2
PWR?
1000?
2017 2012 UAE, ENEC
? ?

Dates according to latest announcements.

Sources:
UIC/WNA information papers and newsletters.
Nuclear Engineering International, handbook.


Uranium mill would process more than rocks


By Dick Kamp

MONTROSE COUNTY — Energy Fuels Inc. has told the Montrose County Planning Commission it wants to process waste and process streams beyond uranium ore at their proposed Paradox Valley Pinon Ridge uranium mill.

The announcement came after public testimony was concluded at a second hearing June 10 in Montrose for a special use permit. The proposed location of the new facility would be about 12 miles east of Paradox in the West End off of state Highway 90.

In public testimony at the first hearing May 19, Energy Fuels representatives said that they had “no plans to process any material other than uranium ore.” This appears to have been the sole public comment on the Montrose County Planning Director Steve White issued a memo to the planning commission prior to

he June 10 hearing that proposed the specific condition that “only raw uranium ore processed on-site may be stored in the tailings cells.”

Late in the June 10 hearing, EF’s CEO George Glasier approached the planning commission to discuss alternatives to White’s proposed feed restriction condition. Durango attorney Travis Stills, who represents mill opponent Paradox Valley Sustainability Association, said he spoke after Glasier’s presentation, even though public comment was closed.

“I told the commission that changing the wording to the condition would open up a can of worms and that I was very uncomfortable with this request,” Stills told the Daily Press. “I had heard EF bandy about several wordings including allowing the mill to process ‘source materials.’ It means any materials having over .05 percent of radioactive substances such as uranium and thorium, or in other words, no limit at all.”

Stills went on to say that Phil Egidi, representing the Colorado Department of Public Health and Environment, concurred with his opinion.

Egidi suggested perhaps the mill could process specific materials as filters from municipal treatment facilities with high radioactivity in the water. Egidi stressed that even though the state has no permit application, that EF and CDPHE have had discussions on what process feed the mill might handle that preceded the county hearings.

Potential process feed discussions had included, according to Egidi, potentially ion resin columns from filters containing uranium from water treatment facilities in southeast and southwest Colorado, uranium from in-situ mining facilities in Wyoming, Nebraska and Texas, that would also be deposited on ion-resin columns after a solution was injected into the ground, and “possibly uranium from EFs own mining water treatment facilities.”

“We have no permit, and unlike Montrose County, we have no deadlines for a permit and we can take the time to get our language right and avoid industrial waste streams such as those that the White Mesa and Cotter (closed Canon City) mills have sought. EF has stressed to us that they are not seeking contracts for industrial radioactive waste,” Egidi said. Egidi anticipates receiving a permit application for in-situ mining, but there are none currently operating, nor under consideration, in the state. Presumably concentrations of uranium from in-situ facilities would be far more concentrated than from most municipal treatment facilities.

“We approached the commission at the end of the June 10 hearing because the state (Egidi), had suggested, between the two hearings, that we process the municipal ion resin filters in order to reduce the costs to municipalities with high uranium and those are to be found throughout the West,” Glasier said Wednesday.

“At the first hearing, we thought that a permit that allowed us to process ore — and we did want to be able to process our own mines’ water treatment filters but hadn’t mentioned that yet — would be acceptable. Those two items are all that we would want to add to the processing restriction on a permit.”

With Egidi referring to municipal water treatment wastes from southern Colorado, and Glasier referring to water wastes throughout the West, it is unclear what the geographic limit for importation of the process material is intended to be.

Critics of the EF proposal have feared the processing of any substances resembling radioactive waste as an open-ended invitation to what they term “false recycling” wherein radioactive waste is dubbed “recycling” because the sender pays a uranium mill a relatively low fee to have waste turned into yellowcake instead of sending it to an expensive, low-level radioactive waste facility. Uranium mills, in turn, profit from a waste stream they are paid to convert to yellowcake instead of paying a toll for uranium ore coming from mines the mill does not own.

Older uranium mills, even the last constructed facilities such as Canon City and White Mesa, Utah, also have a history of water, soil and tailings contamination, and both mills profited largely from processing waste as opposed to ore.

Stills said importation of a few wastes or concentrates such as those from in-situ mines, or from water system filters could open a wide door to processing of other toxic substances and industrial waste as opposed to mining beneficiation.

“I think that we are looking at a special use permit for a mill that cannot make a decent profit on uranium ore and instead wants to get permitted as an industrial uranium-hazardous materials recycler,” Still said.

“That would not be a mining development-related permit in an agricultural area, and if that were the case, this would not be a valid application. Energy Fuels has totally misled the public in these hearings and in past public meetings, and this new information should be a focus of public comment and a new application.

“If EF is not going to build a mill that only processes uranium ore, then let the debate begin.”

White stressed that neither he nor the planning commission had direct knowledge of any discussion of other waste streams prior to the public hearings. As soon as the issue had been raised in a question from the Daily Press, he had included his “ore-only” provision as a staff recommendation and had raised it at both hearings.

“Energy Fuels has asked to submit potential language to us on their process stream and as soon as our attorney (Bob Hill) is available, next week, we will hopefully have something to evaluate. I think that the commission did not feel comfortable with the question of what the mill would process, nor with some water issues such as potentially setting conditions for monitoring over-pumping or actions that could be taken if it occurs. That’s why they continued the hearing to July 1,” White said.

The third hearing will be held that evening at 6 at Friendship Hall. If the planning commission approves a permit there, it could be sent over to the county commissioners for a vote.

White said they will be consulting with Egidi, including discussion on what contaminants can be brought into the county and what the county may not want brought in.

White said it was up to the planning commission to decide whether further public comment would be accepted.

“I would think that if there are issues affecting residents of the county that have not been addressed, that commission members might want to open them up to more comment in the interests of doing a comprehensive analysis,” he said.

White said another unresolved question is the life of the permit. “EF has five years to get moving on the mill and if they do not do so, then the permit would expire. But if there is litigation against them, perhaps we should be amending that condition,” White said.

“Maybe we could add a year in the event that they were in court five years from now. I don’t think it will take the state five years to make a decision.”
source:

Nuclear nations rush to lock in uranium deals


By Cameron French
TORONTO, June 18 (Reuters) - A global shift toward nuclear power is prompting countries to rush to lock in long-term access to tight supplies of uranium, and China and India look to be the next players to get in on the action.

A tie-up between Rosatom, the Russian state-owned producer, and Canada-based miner Uranium One announced this week is just the latest in a series of moves on the part of Asian and European countries to lock in uranium supply to fuel construction of dozens of new reactors over the next decade.

"I think increasingly the supply of reactors is being tied to security of supply of nuclear fuel," said Divya Reddy, an energy analyst with the Eurasia Group in Washington.
Rosatom secured a 17 percent stake in Uranium One and a long-term supply deal in exchange for a half stake in the Karatau mine in Kazakhstan.


Uranium One is also trying to close a C$270 million ($240 million) 20 percent share sale and supply agreement with Japan's Toshiba Corp <6502.t>, Toyko Electric Power Co <9501.t>, and Japan Bank for international Cooperation, while uranium miner Denison Mines recently agreed to sell 20 percent of itself to Korea Electric Power Corp <015760.t>.
Reddy sees more activity from Russia as it strives to expand its influence in the nuclear industry, but said the most likely sources of demand in the longer run will come from Asia, including India, which last year signed a deal ending a three-decade ban on nuclear trade with the United States.
"There is definitely growth in demand from developing countries. China would be the biggest market, India probably next," she said.

China, with the most ambitious nuclear power expansion plans, has been in talks with top uranium miner Cameco about a potential supply deal, a company spokesman confirmed.
Australia is also mulling selling uranium from BHP Billiton's Olympic Dam mine to China, provided it is not used in Beijing's weapons program.
100 NEW REACTORS
Led by China, India and Russia, more than 100 new reactors will be built over over the next decade, Cameco estimates, all part of a global push to reduce dependence on greenhouse gas-producing power sources such as coal.
With new reactors expected to be larger on average than the 426 currently in operation, generating capacity would grow by 28 percent, the company says.
"Over 10 years, the demand for uranium will definitely continue to rise, and there will be a need for new mines and new solutions," said Mike Goldenberg, director of nuclear fuel markets at New York-based Evolution Markets.

Meanwhile, state-run Russian and Kazakh nuclear concerns have been busy signing deals with countries such as China and Japan to export nuclear industry and technology.
Traditionally a small industry with production dominated by Canada in recent years, the uranium sector has come alive of late as rising demand has driven prices up sharply from the $7 a pound they were trading at in 2000.
Spot uranium, which peaked at $136 a pound in 2007, was at $53 a pound this week.
Kazakhstan has leveraged its massive reserves into a rapidly expanding industry, while Australia is also ramping up production with several mines in the planning stage.
Uranium One CEO Jean Nortier said last week that Africa could emerge as the next hot spot for the mineral, where uranium is often found in copper and gold deposits.
Equinox Minerals , for instance, plans to build a uranium mill to process ore from its Lumwana copper mine in Zambia.

Increases in production will be necessary to keep afloat an industry that is already sharply in deficit.

PRODUCTION SHORTFALL
Mined production last year fell short of consumption by about 60 million pounds, with the shortfall made up largely by recycled material and diluted enriched uranium from decommissioned nuclear weapons, sold by Russia under an agreement with Western producers that will end in 2013.

"The Chinese are already out actively sourcing (uranium), and most recently, because they've just recently been allowed back in to the nuclear club, India has been courted by just about every nuclear technology supplier in the world," said George Topping, an analyst at Blackmont Capital in Toronto.

With mid-tier producers such as Uranium One and Denison already having taken on national partners, Topping expects uranium-hungry countries to seek supply deals with top producers such as Cameco BHP and Rio Tinto , and enter deals to finance smaller developers with viable projects.

"(Buying a stake,) that's the first choice, but if you can't have that, then you can finance companies with advanced deposits," he said.
source: www.guardian.co.uk

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