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CLEAN SMART bill reintroduced in Senate
Senators Ben Ray Luján (D., N.M.) and Tim Scott (R., S.C.) have reintroduced legislation aimed at leveraging the best available science and technology at U.S. national laboratories to support the cleanup of legacy nuclear waste.
The Combining Laboratory Expertise to Accelerate Novel Solutions for Minimizing Accumulated Radioactive Toxins (CLEAN SMART) Act, introduced on February 11, would authorize up to $58 million annually to develop, demonstrate, and deploy innovative technologies, targeting reduced costs and safer, faster remediation of sites from the Manhattan Project and Cold War.
P. Barthelemy, R. Berger, R. Boucher, L. Hayet
Nuclear Technology | Volume 26 | Number 2 | June 1975 | Pages 201-214
Technical Paper | Radioisotope | doi.org/10.13182/NT75-A24419
Articles are hosted by Taylor and Francis Online.
In 1971 the French Atomic Energy Commission (CEA) established itself as a candidate for 252Cf commercial encapsulation services. A production facility, designed and built at the Fontenay-aux-Roses Centre for Nuclear Studies, allows handling of up to 10 mg of 252Cf. This unit started operation in Sep. 1973. The main features of the californium facility are: (a) remote manipulation by means of two electrical robots, (b) TIG welding of capsules and assemblies using two machines, with variable positioning of the electrode along the three axis that allows the soldering of pieces as large as 50 mm in diameter and 2 m in length, (c) capsule decontamination by an electrolytic pickling technique, and (d) neutron source emission counting by means of a uranium fission chamber giving relative measurements versus a 252Cf standard with an accuracy of 3%. All sealed sources developed at the CEA are made of 252Cf2O3-Pd cermets encapsulated in stainless steel, Zircaloy, or nickel and are qualified as special form nuclear material. Present applications of 252Cf sealed sources in France are directed toward physical research and nuclear reactor design, nuclear reactor startup and nuclear materials assay, neutron activation analysis development for in situ determinations in the earth science and mineral exploration, and for process control in metallurgy. Furthermore, the CEA is involved in a government-sponsored program on a 252Cf source projector for neutron therapy. For the afterloading interstitial technique, the CEA has designed miniaturized sources made of a 252Cf2O3-Pd cermet containing 0.32 μg of 252Cf sealed in a platinum capsule 0.70 mm in diameter and 4 mm long.