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Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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College students help develop waste-measuring device at Hanford
A partnership between Washington River Protection Solutions (WRPS) and Washington State University has resulted in the development of a device to measure radioactive and chemical tank waste at the Hanford Site. WRPS is the contractor at Hanford for the Department of Energy’s Office of Environmental Management.
Penzhorn R.-D., Berndt U., Kirste E., Hellriegel W., Jung W., Pejsa R., Romer O.
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 723-731
Tritium Processing | Proceedings of the Fifth Topical Meeting on Tritium Technology in Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST95-A30490
Articles are hosted by Taylor and Francis Online.
During commissioning of the PETRA facility all components were tested singly and sequentially using hydrogen isotopes (incl. up to 1.3 g tritium as DT) and relevant impurities. The operation of the facility in conjunction with the required infrastructure systems of the Tritium Laboratory Karlsruhe (TLK) was also demonstrated. To characterize the PETRA PdAg permeator hydrogen break-through curves for H2, De2 and DT as well as He break-through curves for various H2/D2/He gas mixtures were determined at 300 and 400 °C. A suitable method was developed to verify the mechanical integrity of the permeator during runs with tritium. The H2 and D2 permeation losses into the isolation vacuum of the permeator were quantified and compared with model calculations. Hydrogen permeation into the isolation vacuum could be kept at levels low enough to permit an undisturbed continuous operation of the permeator using a ZrCo tritium storage vessel. All pumps and pump combinations were examined with respect to the achievable vacua and compression ratios employing relevant gases and their mixtures. Loop-integrated infrared analysis of high signal and background stability is used to verify the integrity of the permeator and to study the possible occurrence of radiochemical reactions in the gas phase. It was shown that the ZrCo tritium storage vessel of the PETRA facility can be employed avantageously for the handling of tritium when used in combination with a Normetex scroll pump (18 m3/h)/Siemens metal bellows double stage compressor pump sequence. With this combination it is possible to extract at < 320 °C > 98 % of the hydrogen isotopes from the ZrCo storage vessel with a) negligible permeation losses, b) without the danger of disproportionation of the intermetallic compound and c) with minimization of the tritium inventory in the facility.