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Measurement of gamma and neutron radiations inside spent fuel assemblies with passive detectors
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SYSNO ASEP 0352318 Document Type J - Journal Article R&D Document Type Journal Article Subsidiary J Článek ve WOS Title Measurement of gamma and neutron radiations inside spent fuel assemblies with passive detectors Author(s) Viererbl, L. (CZ)
Lahodová, Z. (CZ)
Voljanskij, A. (CZ)
Klupák, V. (CZ)
Koleška, M. (CZ)
Cabalka, M. (CZ)
Turek, Karel (UJF-V) ORCID, SAISource Title Nuclear Instruments & Methods in Physics Research Section A. - : Elsevier - ISSN 0168-9002
Roč. 652, č. 1 (2011), s. 90-93Number of pages 5 s. Language eng - English Country NL - Netherlands Keywords fuel assembly ; spent fuel ; track detector Subject RIV JF - Nuclear Energetics CEZ AV0Z10480505 - UJF-V (2005-2011) UT WOS 000295765000023 DOI 10.1016/j.nima.2010.09.022 Annotation During operation of a fission nuclear reactor, many radionuclides are generated in fuel by fission and activation of 235U, 238U and other nuclides present in the assembly. After removal of a fuel assembly from the core, these radionuclides are sources of different types of radiation. Gamma and neutron radiation emitted from an assembly can be non-destructively detected with different types of detectors. In this paper, a new method of measurement of radiation from a spent fuel assembly is presented. It is based on usage of passive detectors, such as alanine dosimeters for gamma radiation and track detectors for neutron radiation. Measurements are made on the IRT-2M spent fuel assemblies used in the LVR-15 research reactor. During irradiation of detectors, the fuel assembly is located in a water storage pool at a depth of 6 m. Workplace Nuclear Physics Institute Contact Markéta Sommerová, sommerova@ujf.cas.cz, Tel.: 266 173 228 Year of Publishing 2012
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