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

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F61389005%3A_____%2F11%3A00352318" target="_blank" >RIV/61389005:_____/11:00352318 - isvavai.cz</a>

Výsledek na webu

<a href="http://dx.doi.org/10.1016/j.nima.2010.09.022" target="_blank" >http://dx.doi.org/10.1016/j.nima.2010.09.022</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.nima.2010.09.022" target="_blank" >10.1016/j.nima.2010.09.022</a>

Jazyk výsledku

angličtina

Název v původním jazyce

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

Popis výsledku v původním jazyce

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 ofdifferent 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.

Název v anglickém jazyce

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

Popis výsledku anglicky

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 ofdifferent 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.

Druh

J_x - Nezařazeno - Článek v odborném periodiku (Jimp, Jsc a Jost)

CEP obor

JF - Jaderná energetika

OECD FORD obor

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Projekt

—

Návaznosti

Z - Vyzkumny zamer (s odkazem do CEZ)

Rok uplatnění

2011

Kód důvěrnosti údajů

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Název periodika

Nuclear Instruments & Methods in Physics Research Section A

ISSN

0168-9002

e-ISSN

—

Svazek periodika

652

Číslo periodika v rámci svazku

1

Stát vydavatele periodika

NL - Nizozemsko

Počet stran výsledku

5

Strana od-do

90-93

Kód UT WoS článku

000295765000023

EID výsledku v databázi Scopus

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