排序方式: 共有10条查询结果,搜索用时 15 毫秒
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N. N. Egorov M. A. Zakharov L. N. Lazarev R. I. Lyubtsev A. S. Nikiforov M. V. Strakhov E. A. Filippov 《Atomic Energy》1992,72(2):148-150
Department of the Atomic Energy Industry. 相似文献
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V. I. Beznosyuk B. Ya. Galkin A. B. Kolyadin A. P. Krinitsin R. I. Lyubtsev Yu. S. Fedorov 《Radiochemistry》2007,49(4):380-385
Within the framework of the development of a combined scheme for processing WWER-1000 spent nuclear fuel, head operations such as chemical breaking-up of fuel cladding and voloxidation of the fuel with removal of volatile fission products were studied experimentally. 相似文献
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Galkin B. Ya. Isupov V. K. Kolyadin A. B. Kocherov N. P. Lyubtsev R. I. Nosov A. A. Rimskii-Korsakov A. A. 《Radiochemistry》2002,44(2):174-177
The effective neutron capture cross section of 129I was determined at irradiation of 11.3±0.55 mg of KI (83.5% 129I and 16.5% 127I) for 6 h in a V10 channel of the beryllium reflector of VVR-M water-cooled water-moderated reactor (PINF) at average power of 12 MW. The neutron spectrum was measured by the activation procedure. For this purpose a series of thermal, resonance, and threshold detectors and a weighed portion of iodine were irradiated. The neutron spectrum was restored from the -ray spectra of these samples by the best fit procedure. The neutron capture cross section of 129I, averaged over the neutron spectrum in the beryllium reflector of VVR-M reactor, was 17.8±3.2 b. The activities of products formed from a model 127I portion of iodine were irradiated. The neutron spectrum was restored from the -ray spectra of these samplesby the best fit procedure. The neutron capture cross section of 129I, averaged over the neutron spectrum in theberyllium reflector of VVR-M reactor, was 17.8±3.2 b. The activities of products formed from a model 127Isample irradiated in a loop of VVR-M reactor under steady-state conditions were calculated. 相似文献
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D. N. Bykhovskii B. Ya. Galkin B. Ya. Zilberman V. M. Esimantovskii A. P. Krinitsyn R. I. Lyubtsev V. F. Saprykin L. V. Sytnik V. I. Ryazantsev Yu. S. Fedorov D. N. Shishkin O. V. Shmidt 《Radiochemistry》2007,49(6):613-617
Several stages of the combined process for WWER-1000 spent fuel reprocessing are experimentally tested, including dissolution of fluoride cinder formed after fluoridation of the fuel and distillation of the essential part of uranium hexafluoride, and also separation and purification of plutonium, neptunium, and residual uranium. 相似文献
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