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AbstractAbstract
[en] Deuterium and tritium gases are occluded in uranium powder for release into neutron generator tubes. The uranium powder is contained in stainless steel bottles, termed ''beds.'' If these beds become damaged, the gases must be removed and the uranium oxidized in order not to be flammable before shipment to ERDA disposal grounds. This paper describes the system and methods designed for the controlled degassing and oxidation process. The system utilizes sputter-ion, cryo-sorption and bellows pumps for removing the gases from the heated source bed. Removing the tritium gas is complicated by the shielding effect of helium-3, a byproduct of tritium decay. This effect is minimized by incremental pressure changes, or ''batch'' processing. To prevent runaway exothermic reaction, oxidation of the uranium bed is also done incrementally, or by ''batch'' processing, rather than by continuous flow. The paper discusses in detail the helium-3 shielding effect, leak checks that must be made during processing, bed oxidation, degree of gas depletion, purity of gases sorbed from beds, radioactivity of beds, bed disposal and system renovation
Original Title
After removal of deuterium, tritium for disposal
Primary Subject
Source
23 Sep 1977; 14 p; Available from NTIS., PC A02/MF A01
Record Type
Report
Report Number
Country of publication
ACTINIDES, BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, CHEMICAL REACTIONS, ELEMENTS, EVEN-ODD NUCLEI, HELIUM ISOTOPES, HYDROGEN ISOTOPES, ISOTOPES, LIGHT NUCLEI, MANAGEMENT, METALS, NUCLEI, ODD-EVEN NUCLEI, ODD-ODD NUCLEI, RADIOISOTOPES, STABLE ISOTOPES, WASTE MANAGEMENT, YEARS LIVING RADIOISOTOPES
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