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Experimental study of {sup 238}U Doppler reactivity worth in FCA XVI-1 and XVI-2 cores

Technical Report:

Abstract

Doppler reactivity worths of natural uranium samples were measured in metallic fueled cores, FCA XVI-1 and XVI-2, using a sample heating technique. In a metallic fueled LMFBR, the neutron spectrum is generally harder than a similar size oxide fueled LMFBR owing to the luck of oxygen. The accuracy of Doppler effect calculation for a harder neutron spectrum was evaluated by comparing C/E values of Doppler reactivity worth in oxide fueled cores and in metallic fueled cores using FCA experiments. It was found that calculation using 70-group constant set JFS-3-J2 underestimates {sup 238}U Doppler reactivity worth in metallic fueled cores. An inadequate treatment of resonance parameters of {sup 238}U above 50 keV in JENDL-2 is one of the reasons for this underestimation. In JENDL-2 the resonance parameters of {sup 238}U above 50 keV are not included, and hence JFS-3-J2 which is processed from JENDL-2 does not have a self-shielding factor table above 40.9 keV of {sup 238}U. When the contribution of this energy region for Doppler reactivity worth was corrected using ENDF/B-VI, which includes resonance parameters of {sup 238}U up to 149 keV, the JFS-3-J2 based calculation gave 13% higher values for metallic sample experiments and 8% for oxide samples. Even  More>>
Authors:
Oigawa, Hiroyuki; Okajima, Shigeaki; Mukaiyama, Takehiko; Satoh, Kunio [1] 
  1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Publication Date:
Aug 01, 1992
Product Type:
Technical Report
Report Number:
JAERI-M-92-113
Reference Number:
SCA: 220600; PA: JPN-92:012157; SN: 93000919859
Resource Relation:
Other Information: PBD: Aug 1992
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; REACTOR CORES; LMFBR TYPE REACTORS; URANIUM 238; DOPPLER EFFECT; FCA REACTOR; REACTIVITY WORTHS; SOLID FUELS; NEUTRON SPECTRA; SELF-SHIELDING; CROSS SECTIONS; FAST NEUTRONS; TEMPERATURE DEPENDENCE; 220600; RESEARCH, TEST, TRAINING, PRODUCTION, IRRADIATION, MATERIALS TESTING REACTORS
OSTI ID:
10112581
Research Organizations:
Japan Atomic Energy Research Inst., Tokyo (Japan)
Country of Origin:
Japan
Language:
Japanese
Other Identifying Numbers:
Other: ON: DE93754292; TRN: JP9212157
Availability:
OSTI; NTIS; INIS
Submitting Site:
JPN
Size:
41 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Oigawa, Hiroyuki, Okajima, Shigeaki, Mukaiyama, Takehiko, and Satoh, Kunio. Experimental study of {sup 238}U Doppler reactivity worth in FCA XVI-1 and XVI-2 cores. Japan: N. p., 1992. Web.
Oigawa, Hiroyuki, Okajima, Shigeaki, Mukaiyama, Takehiko, & Satoh, Kunio. Experimental study of {sup 238}U Doppler reactivity worth in FCA XVI-1 and XVI-2 cores. Japan.
Oigawa, Hiroyuki, Okajima, Shigeaki, Mukaiyama, Takehiko, and Satoh, Kunio. 1992. "Experimental study of {sup 238}U Doppler reactivity worth in FCA XVI-1 and XVI-2 cores." Japan.
@misc{etde_10112581,
title = {Experimental study of {sup 238}U Doppler reactivity worth in FCA XVI-1 and XVI-2 cores}
author = {Oigawa, Hiroyuki, Okajima, Shigeaki, Mukaiyama, Takehiko, and Satoh, Kunio}
abstractNote = {Doppler reactivity worths of natural uranium samples were measured in metallic fueled cores, FCA XVI-1 and XVI-2, using a sample heating technique. In a metallic fueled LMFBR, the neutron spectrum is generally harder than a similar size oxide fueled LMFBR owing to the luck of oxygen. The accuracy of Doppler effect calculation for a harder neutron spectrum was evaluated by comparing C/E values of Doppler reactivity worth in oxide fueled cores and in metallic fueled cores using FCA experiments. It was found that calculation using 70-group constant set JFS-3-J2 underestimates {sup 238}U Doppler reactivity worth in metallic fueled cores. An inadequate treatment of resonance parameters of {sup 238}U above 50 keV in JENDL-2 is one of the reasons for this underestimation. In JENDL-2 the resonance parameters of {sup 238}U above 50 keV are not included, and hence JFS-3-J2 which is processed from JENDL-2 does not have a self-shielding factor table above 40.9 keV of {sup 238}U. When the contribution of this energy region for Doppler reactivity worth was corrected using ENDF/B-VI, which includes resonance parameters of {sup 238}U up to 149 keV, the JFS-3-J2 based calculation gave 13% higher values for metallic sample experiments and 8% for oxide samples. Even after this correction, the calculation still gave smaller Doppler reactivity worths than the measurements, and the ratios of calculated value to experimental one vary widely from 0.6 to 1.0. (author).}
place = {Japan}
year = {1992}
month = {Aug}
}