Measurement of gamma and neutron radiations inside spent fuel assemblies with passive detectors

0352318 - ÚJF 2012 RIV NL eng J - Journal Article
Viererbl, L. - Lahodová, Z. - Voljanskij, A. - Klupák, V. - Koleška, M. - Cabalka, M. - Turek, Karel
Measurement of gamma and neutron radiations inside spent fuel assemblies with passive detectors.
Nuclear Instruments & Methods in Physics Research Section A. Roč. 652, č. 1 (2011), s. 90-93. ISSN 0168-9002. E-ISSN 1872-9576
Institutional research plan: CEZ:AV0Z10480505
Keywords : fuel assembly * spent fuel * track detector
Subject RIV: JF - Nuclear Energetics
Impact factor: 1.207, year: 2011

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.
Permanent Link: http://hdl.handle.net/11104/0191851