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

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F11%3A%230000642" target="_blank" >RIV/26722445:_____/11:#0000642 - 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 radiation inside of 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. After removal of a fuel assembly from the core, these radionuclides are sources of different types of radiation. 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 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. Detectors are inserted into central hole of the assembly, irradiated for a defined time interval, and after the detectors removed from the assembly, gamma dose or neutron fluence are evaluated. Measured profiles of gamma dose rate and neutron fluence rate inside of the spent fuel assembly are presented. This measurement can be used to evaluate relativ

Název v anglickém jazyce

Measurement of gamma and neutron radiation inside of 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. After removal of a fuel assembly from the core, these radionuclides are sources of different types of radiation. 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 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. Detectors are inserted into central hole of the assembly, irradiated for a defined time interval, and after the detectors removed from the assembly, gamma dose or neutron fluence are evaluated. Measured profiles of gamma dose rate and neutron fluence rate inside of the spent fuel assembly are presented. This measurement can be used to evaluate relativ

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 and Methods in Physics Research A

ISSN

0168-9002

e-ISSN

—

Svazek periodika

652

Číslo periodika v rámci svazku

1

Stát vydavatele periodika

CZ - Česká republika

Počet stran výsledku

4

Strana od-do

90-93

Kód UT WoS článku

000295765000023

EID výsledku v databázi Scopus

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