Release of xenon-137 and iodine-137 from UO/sub 2/ pellet by pulse neutron irradiation at NSRR Ishiwatari, N; Nagai, H [Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment] 22 GENERAL STUDIES OF NUCLEAR REACTORS; CESIUM 137; FISSION YIELD; FUEL PELLETS; FISSION PRODUCT RELEASE; IODINE 137; URANIUM DIOXIDE; EXPERIMENTAL DATA; FISSION PRODUCTS; IRRADIATION; LEAKS; NSRR REACTOR; PULSED NEUTRON TECHNIQUES; XENON 137; ACTINIDE COMPOUNDS; ALKALI METAL ISOTOPES; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CESIUM ISOTOPES; CHALCOGENIDES; DATA; ENRICHED URANIUM REACTORS; EVEN-ODD NUCLEI; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; INFORMATION; INTERMEDIATE MASS NUCLEI; IODINE ISOTOPES; ISOTOPES; MATERIALS; MINUTES LIVING RADIOISOTOPES; MIXED SPECTRUM REACTORS; NUCLEAR REACTION YIELD; NUCLEI; NUMERICAL DATA; ODD-EVEN NUCLEI; OXIDES; OXYGEN COMPOUNDS; PELLETS; PULSED REACTORS; RADIOACTIVE MATERIALS; RADIOISOTOPES; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SECONDS LIVING RADIOISOTOPES; SOLID HOMOGENEOUS REACTORS; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS; XENON ISOTOPES; YEARS LIVING RADIOISOTOPES; YIELDS; 220300* - Nuclear Reactor Technology- Fuel Elements A radiochemical procedure was established to estimate the amount of volatile fission products nuclides released from UO/sub 2/ pellet by the pulse neutron irradiation at the NSRR. The /sup 137/Cs amounts in the fuel rods after irradiation at the NSRR were measured to clarify release behavior of fission products (/sup 137/Xe and /sup 137/I) from oxide fuel under the reactivity initiated accident condition. The amounts of /sup 137/Xe and /sup 137/I released from the UO/sub 2/ pellet were estimated from the measurement of /sup 137/Cs. All UO/sub 2/ pellets before irradiation at the NSRR were fresh. The nuclides of /sup 137/Xe and /sup 137/I generated in UO/sub 2/ pellet of fuel rod by irradiation at the NSRR were released from the pellet in relation with the vaporization phenomenon after melting of UO/sub 2/ pellet. At the deposition energy higher than 340--350cal/g UO/sub 2/, about 60% of /sup 137/Xe and /sup 137/I were released from the pellet of fuel rod, at maximum. At the deposition energy lower than 340 --350cal/g UO/sub 2/, /sup 137/Xe and /sup 137/I in the UO/sub 2/ pellet of fuel rod were scarcely released out. Japan 1981-11-01 Japanese Journal Article Journal Name: Nippon Genshiryoku Gakkaishi; (Japan); Journal Volume: 23:11 Medium: X; Size: Pages: 843-850 https://doi.org/ [] 23:11 Journal ID: CODEN: NGEGA AIX-14-776980; EDB-83-176343 2010-05-12 5714707