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Strontium-90 , nuclear fuel

SREX [Strontium extraction] A process for removing strontium-90 from aqueous wastes from nuclear fuel processing, by solvent extraction into a solution of 18-crown-6 in octanol. Developed by E. P. Horwitz at the Argonne National Laboratory, Chicago, IL, in 1990. [Pg.253]

Highly pure lanthanum oxide is used to make optical glass of high refractive index for camera lenses. It also is used to make glass fibers. The oxide also is used to improve thermal and electrical properties of barium and strontium titanates. Other applications are in glass polishes carbon arc electrodes fluorescent type phosphors and as a diluent for nuclear fuels. In such apph-cations, lanthinum oxide is usually combined with other rare earth oxides. [Pg.451]

Some zeolites have a strong affinity for particular cations. Clinoptilolite (HEU) is a naturally occurring zeolite which sequesters caesium, and is used by British Nuclear Fuels (BNFL) to remove Cs from radioactive waste, exchanging its own Na ions for the radioactive Cs cations. Similarly, zeolite A can be used to recover radioactive strontium. Zeolites were heavily used in the clean up operations after the Chernobyl and Three Mile Island incidents. [Pg.320]

The counting techniques described in this paper are also readily applicable to studies of "hot radioactive waste (z.e.j radioactive waste from reprocessed nuclear fuel). With this type of material, the cesium can be analyzed as 30-y (662-keV y), the RE as 13-y Eu (964-keV and 1408-keV y), strontium as 28-y Sr (after chemical separation and beta counting), and the actinides by group separation and alpha counting. [Pg.124]

Riddle, C.L., Baker, J.D., Law, J.D. et al. 2004. Development of a novel solvent for the simultaneous separation of strontium and cesium from dissolved spent nuclear fuel solutions. Americas Nuclear Energy Symposium (ANES 2004), Deauville Beach Resort, Miami Beach, FL, October 3-6. [Pg.60]

Todd, T.A., Law, J.D., Herbst, R.S. et al. 2005. Advanced technologies for the simultaneous separation of cesium and strontium from spent nuclear fuel. WM 05 Conf, February 27 to March 3, Tucson, AZ. [Pg.60]

Galkin, B.Ya., Shishkin, D.N. 2001. Extraction withdrawal of cesium and strontium radionuclides from the solution of spent nuclear fuel. In Back-End of the Fuel Cycle From Research to Solutions. GLOBAL 2001, September 9-13, Paris, France. [Pg.61]

Kuno, Y., Sato, S., Ohno, E., and Masui, J., Rapid determination of strontium-90 in highly radioactive solutions of nuclear fuel reprocessing plant, Anal. Sci., 9,195-198, 1993. [Pg.559]

These results are consistent with laboratory measurements of the effects of pH and oxidation state on the leachability of nuclear fuel particles (Kashparov et al, 2000). The increased leachability of the oxidized fuel particles may be due to (i) an increased solubility because of the change in oxidation state (ii) the higher surface area of the highly fractured oxidized particles or (iii) the diffusion of radionuclides (strontium, caesium) to grain boundaries and particle surfaces during the heating and oxidation process. [Pg.4784]

Markham OD, Hafford DK, Autenrieth RE. 1980. Strontium-90 concentrations in pronghorn antelope bones near a nuclear fuel reprocessing plant. Health Phys 38 811-816. [Pg.366]

Many people, including environmentalists, regard nuclear fission as a highly undesirable method of energy production. Many fission products such as strontium-90 are dangerous radioactive isotopes with long half-lives. Plutonium-239, used as a nuclear fuel and produced in breeder reactors, is one of the most toxic substances known. It is an alpha emitter with a half-hfe of 24,400 yr. [Pg.921]

Storage of spent nuclear fuel poses a major problem because the fission products are extremely radioactive. It is estimated that 20 half-lives are required for their radioactivity to reach levels acceptable for biological exposure. Based on the 28.8-yr half-life of strontium-90, one of the longer-lived and most dangerous of the products, the wastes must be stored for 600 years. Plutonium-239 is one of the by-products present in spent fuel elements. It is formed by absorption of a neutron by uranium-238, followed by two successive beta emissions. (Remember that most of the uranium in the fuel elements is uranium-238.) If the elements are reprocessed, the plutonium-239 is largely recovered because it can be used as a nuclear fiieL However, if the plutonium is not removed, spent elements must be stored for a very long time because plutonium-239 has a half-life of24,000 yr. [Pg.900]

There are many examples of the studies on SLM for nuclear applications in the literature. SLMs were tested for high-level radioactive waste treatment combined with removal of actinides and other fission products from the effluents from nuclear fuel reprocessing plants. The recovery of the species, such as uranium, plutonium, thorium, americium, cerium, europium, strontium, and cesium, was investigated in vari-ons extracting-stripping systems. Selective permeation... [Pg.694]

Law, J.D., T.G. Cam, R.S. Herbst, D.H. Meikrantz, D.R. Peterman, C.L. Riddle, T.A. Todd, and J.L. Tripp. 2006. Development of cesium and strontium separation and immobilization technologies in support of an advanced nuclear fuel cycle. WM 06 Proceedings of the Waste Management... [Pg.464]

Strontium ( Sr) is a fission product that is common in spent fuel. Nuclear fuel processing, above ground nuclear weapons testing, and nuclear accidents are primary environmental sources of Sr. Strontium-90 also is released by nuclear power plants, submarine propulsion reactors, and radioactive waste disposal in the oceans. Sr has a half-life of roughly 29 yr. The decay products are Yt (ri/2 = 64 h, with the emission of a 546 keV maximum energy P particle) and then the stable Zr with the emission of a 2284 keV maximum energy p particle from Infre-... [Pg.18]

Sr and Cs are ubiquitous in the processing of nuclear fuel and, subsequently, in low-level radioactive wastes. Sr and Cs also were released during the Chernobyl accident. In groundwater, dissolved Cs tends to be present in the Cs form. Cesium sorbs strongly to the clay fraction in soils (K are typically >1000 mL g ) and often the fraction that can be subsequently desorbed is small—around 15%—see the review of Brady et al. (1999). Strontium behaves similarly to Ca in soils and sorbs appreciably to soil components—a median value for soil of 27... [Pg.176]

Spent fuel from a reactor contains unused uranium as well as plutonium-239 which has been created by bombardment of neutrons during the fission process. Mixed with these useful materials are other highly radioactive and hazardous fission products, such as cesium-137 and strontium-90. Since reprocessed fuels contain plutonium, well suited for making nuclear weapons, concern has been expressed over the possible capture of some of this material by agents or terrorists operating on behalf of unfriendly governments that do not have a nuclear weapons capability. [Pg.1122]


See other pages where Strontium-90 , nuclear fuel is mentioned: [Pg.1662]    [Pg.1708]    [Pg.270]    [Pg.71]    [Pg.61]    [Pg.135]    [Pg.316]    [Pg.35]    [Pg.213]    [Pg.236]    [Pg.238]    [Pg.277]    [Pg.456]    [Pg.713]    [Pg.263]    [Pg.87]    [Pg.124]    [Pg.364]    [Pg.194]    [Pg.194]    [Pg.197]    [Pg.366]   


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Strontium-90 , nuclear fuel reprocessing

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