Published October 2013 | Version v1
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GEANT4 simulation study of a gamma-ray detector for neutron resonance densitometry

Creators

  • 1. Japan Atomic Energy Agency, Nuclear Science and Engineering Directorate, Tokai, Ibaraki (Japan)

Description

A design study of a gamma-ray detector for neutron resonance densitometry was made with GEANT4. The neutron resonance densitometry, combining neutron resonance transmission analysis and neutron resonance capture analysis, is a non-destructive technique to measure amounts of nuclear materials in melted fuels of the Fukushima Daiichi nuclear power plants. In order to effectively quantify impurities in the melted fuels via prompt gamma-ray measurements, a gamma-ray detector for the neutron resonance densitometry consists of cylindrical and well type LaBr3 scintillators. The present simulation showed that the proposed gamma-ray detector suffices to clearly detect the gamma rays emitted by 10B(n, αγ) reaction in a high environmental background due to 137Cs radioactivity with its Compton edge suppressed at a considerably small level. (author)

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Part of:
Proceedings of the 2012 symposium on nuclear data

Additional details

Publishing Information

Imprint Title
Proceedings of the 2012 symposium on nuclear data
Imprint Pagination
214 p.
Journal Page Range
p. 119-124
Report number
JAEA-Conf--2013-002

Conference

Title
2012 symposium on nuclear data
Dates
15-16 Nov 2012
Place
Kumatori, Osaka (Japan)

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
45087669
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S46: INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTERIZED SIMULATION; DIAGNOSTIC TECHNIQUES; FEASIBILITY STUDIES; FUKUSHIMA-1 REACTOR; FUKUSHIMA-2 REACTOR; FUKUSHIMA-3 REACTOR; MELTDOWN; NONDESTRUCTIVE ANALYSIS; NUCLEAR FUELS; NUCLEAR MATERIALS MANAGEMENT; PROMPT GAMMA RADIATION; RADIATION DETECTORS
Descriptors DEC
ACCIDENTS; BWR TYPE REACTORS; CHEMICAL ANALYSIS; ELECTROMAGNETIC RADIATION; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; GAMMA RADIATION; IONIZING RADIATIONS; MANAGEMENT; MATERIALS; MEASURING INSTRUMENTS; POWER REACTORS; RADIATIONS; REACTOR ACCIDENTS; REACTOR MATERIALS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
12 refs., 5 figs.
Secondary number(s)
INDC(JPN)--198