Experimental studies of fission product release from model fuel elements at the physical start-up of the IVG.1M research reactor; Applied Radiation and Isotopes; Vol. 201

Dettagli Bibliografici
Parent link:Applied Radiation and Isotopes.— .— Amsterdam: Elsevier Science Publishing Company Inc.
Vol. 201.— 2023.— Article number 111023, 6 p.
Altri autori: Svetachev S. N. Stanislav Nikolaevich, Popov Yu. A. Yury Anatoljevich, Sabitova R. Radmila, Bedenko S. V. Sergey Vladimirovich, Prozorova I. V. Irina Valentinovna, Medetbekov B. S. Berik Sakenovich
Riassunto:Title screen
During the physical start-up of the IVG.1M research reactor, which involved the conversion to low-enriched uranium fuel, various studies were conducted using physical mock-ups of the fuel assemblies. The mock-up consisted of 468 model low-enriched uranium fuel elements that were cut into three sections without end coatings at the cut locations. This configuration allowed for the simulation of fuel element decompression and the experimental determination of fission product release into the coolant. The coolant samples obtained from the mock-up were analyzed using a gamma-spectrometer equipped with a high-purity germanium detector. As a result of the studies, the activities of fission products in the coolant and the averaged relative fission product release were determined. The relative release is defined as the ratio of the release rate of reference fission products to its birth rate. For the first time, fission product release was experimentally obtained in a situation simulating the decompression of IVG.1M fuel cladding
Текстовый файл
AM_Agreement
Lingua:inglese
Pubblicazione: 2023
Soggetti:
Accesso online:https://doi.org/10.1016/j.apradiso.2023.111023
Natura: Elettronico Capitolo di libro
KOHA link:https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=680247

MARC

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330 |a During the physical start-up of the IVG.1M research reactor, which involved the conversion to low-enriched uranium fuel, various studies were conducted using physical mock-ups of the fuel assemblies. The mock-up consisted of 468 model low-enriched uranium fuel elements that were cut into three sections without end coatings at the cut locations. This configuration allowed for the simulation of fuel element decompression and the experimental determination of fission product release into the coolant. The coolant samples obtained from the mock-up were analyzed using a gamma-spectrometer equipped with a high-purity germanium detector. As a result of the studies, the activities of fission products in the coolant and the averaged relative fission product release were determined. The relative release is defined as the ratio of the release rate of reference fission products to its birth rate. For the first time, fission product release was experimentally obtained in a situation simulating the decompression of IVG.1M fuel cladding 
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