Fission Rate Ratios of FCA-IX Assemblies as Integral Experiment for Assessment of TRU’s Fission Cross Sections

At the fast critical assembly (FCA) of JAEA, central fission rate ratios for TRU such as 237Np, 238Pu, 239Pu, 242Pu, 241Am, 243Am, and 244Cm were measured in the seven uraniumfueled assemblies (FCA-IX assemblies) with systematically changed neutron spectra. The FCA-IX assemblies were constructed wit...

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Main Authors: Fukushima Masahiro, Tsujimoto Kazufumi, Okajima Shigeaki
Format: Article
Language:English
Published: EDP Sciences 2016-01-01
Series:EPJ Web of Conferences
Online Access:http://dx.doi.org/10.1051/epjconf/201611107002
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spelling doaj-d9e43cd1cd934d68bc7f92658ece4ad72021-08-02T04:14:44ZengEDP SciencesEPJ Web of Conferences2100-014X2016-01-011110700210.1051/epjconf/201611107002epjconf_wonder2016_07002Fission Rate Ratios of FCA-IX Assemblies as Integral Experiment for Assessment of TRU’s Fission Cross SectionsFukushima Masahiro0Tsujimoto Kazufumi1Okajima Shigeaki2Japan Atomic Energy Agency (JAEA)Japan Atomic Energy Agency (JAEA)Japan Atomic Energy Agency (JAEA)At the fast critical assembly (FCA) of JAEA, central fission rate ratios for TRU such as 237Np, 238Pu, 239Pu, 242Pu, 241Am, 243Am, and 244Cm were measured in the seven uraniumfueled assemblies (FCA-IX assemblies) with systematically changed neutron spectra. The FCA-IX assemblies were constructed with simplicity both in geometry and composition. By virtue of these FCA-IX assemblies where the simple combinations of uranium fuel and diluent (graphite and stainless steel) in their core regions were systematically varied, the neutron spectra of them cover from the intermediate to fast one. Taking their advantages, benchmark models with respect to the central fission rate ratios had been recently developed for the evaluation of the TRU’s fission cross sections. As an application of these benchmark models, the Japanese Evaluated Nuclear Data Library JENDL-4.0 was utilized by a Monte Carlo calculation code. Several results show large discrepancies between the calculation and experimental values. The benchmark models would be well suited for the evaluation and modification of the nuclear data for the TRU’s fission cross sections.http://dx.doi.org/10.1051/epjconf/201611107002
collection DOAJ
language English
format Article
sources DOAJ
author Fukushima Masahiro
Tsujimoto Kazufumi
Okajima Shigeaki
spellingShingle Fukushima Masahiro
Tsujimoto Kazufumi
Okajima Shigeaki
Fission Rate Ratios of FCA-IX Assemblies as Integral Experiment for Assessment of TRU’s Fission Cross Sections
EPJ Web of Conferences
author_facet Fukushima Masahiro
Tsujimoto Kazufumi
Okajima Shigeaki
author_sort Fukushima Masahiro
title Fission Rate Ratios of FCA-IX Assemblies as Integral Experiment for Assessment of TRU’s Fission Cross Sections
title_short Fission Rate Ratios of FCA-IX Assemblies as Integral Experiment for Assessment of TRU’s Fission Cross Sections
title_full Fission Rate Ratios of FCA-IX Assemblies as Integral Experiment for Assessment of TRU’s Fission Cross Sections
title_fullStr Fission Rate Ratios of FCA-IX Assemblies as Integral Experiment for Assessment of TRU’s Fission Cross Sections
title_full_unstemmed Fission Rate Ratios of FCA-IX Assemblies as Integral Experiment for Assessment of TRU’s Fission Cross Sections
title_sort fission rate ratios of fca-ix assemblies as integral experiment for assessment of tru’s fission cross sections
publisher EDP Sciences
series EPJ Web of Conferences
issn 2100-014X
publishDate 2016-01-01
description At the fast critical assembly (FCA) of JAEA, central fission rate ratios for TRU such as 237Np, 238Pu, 239Pu, 242Pu, 241Am, 243Am, and 244Cm were measured in the seven uraniumfueled assemblies (FCA-IX assemblies) with systematically changed neutron spectra. The FCA-IX assemblies were constructed with simplicity both in geometry and composition. By virtue of these FCA-IX assemblies where the simple combinations of uranium fuel and diluent (graphite and stainless steel) in their core regions were systematically varied, the neutron spectra of them cover from the intermediate to fast one. Taking their advantages, benchmark models with respect to the central fission rate ratios had been recently developed for the evaluation of the TRU’s fission cross sections. As an application of these benchmark models, the Japanese Evaluated Nuclear Data Library JENDL-4.0 was utilized by a Monte Carlo calculation code. Several results show large discrepancies between the calculation and experimental values. The benchmark models would be well suited for the evaluation and modification of the nuclear data for the TRU’s fission cross sections.
url http://dx.doi.org/10.1051/epjconf/201611107002
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