Home / Publications / Journals / Nuclear Technology / Volume 16 / Number 3
Nuclear Technology / Volume 16 / Number 3 / December 1972 / Pages 568-569
Technical Note / Radioisotope / dx.doi.org/10.13182/NT72-A31227
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A method for the production of fission gas isotopes has been developed which is particularly suitable for research reactors lacking extensive hot cell and high level liquid waste handling facilities. The method centers about the development of very high surface area 235U target material. Insertion of this target material into the reactor neutron flux permits removal of gaseous fission products from the target for further processing and utilization outside the reactor.