Abstract
For criticality safety evaluation of burnup fuel, the general-purpose burnup calculation code, SWAT, was revised, and its precision was confirmed through comparison with other results from OECD/NEA's burnup credit benchmarks. Effect by replacing the evaluated nuclear data from JENDL-3.2 to ENDF/B-VI and JEF-2.2 was also studied. Correction factors were derived for conservative evaluation of nuclide concentrations obtained with the simplified burnup code ORIGEN2.1. The critical masses of curium were calculated and evaluated for nuclear criticality safety management of minor actinides. (author)
Okuno, Hiroshi;
Suyama, Kenya;
Nomura, Yasushi
[1]
- Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Citation Formats
Okuno, Hiroshi, Suyama, Kenya, and Nomura, Yasushi.
Researches on nuclear criticality safety evaluation.
Japan: N. p.,
2003.
Web.
Okuno, Hiroshi, Suyama, Kenya, & Nomura, Yasushi.
Researches on nuclear criticality safety evaluation.
Japan.
Okuno, Hiroshi, Suyama, Kenya, and Nomura, Yasushi.
2003.
"Researches on nuclear criticality safety evaluation."
Japan.
@misc{etde_20479051,
title = {Researches on nuclear criticality safety evaluation}
author = {Okuno, Hiroshi, Suyama, Kenya, and Nomura, Yasushi}
abstractNote = {For criticality safety evaluation of burnup fuel, the general-purpose burnup calculation code, SWAT, was revised, and its precision was confirmed through comparison with other results from OECD/NEA's burnup credit benchmarks. Effect by replacing the evaluated nuclear data from JENDL-3.2 to ENDF/B-VI and JEF-2.2 was also studied. Correction factors were derived for conservative evaluation of nuclide concentrations obtained with the simplified burnup code ORIGEN2.1. The critical masses of curium were calculated and evaluated for nuclear criticality safety management of minor actinides. (author)}
place = {Japan}
year = {2003}
month = {Oct}
}
title = {Researches on nuclear criticality safety evaluation}
author = {Okuno, Hiroshi, Suyama, Kenya, and Nomura, Yasushi}
abstractNote = {For criticality safety evaluation of burnup fuel, the general-purpose burnup calculation code, SWAT, was revised, and its precision was confirmed through comparison with other results from OECD/NEA's burnup credit benchmarks. Effect by replacing the evaluated nuclear data from JENDL-3.2 to ENDF/B-VI and JEF-2.2 was also studied. Correction factors were derived for conservative evaluation of nuclide concentrations obtained with the simplified burnup code ORIGEN2.1. The critical masses of curium were calculated and evaluated for nuclear criticality safety management of minor actinides. (author)}
place = {Japan}
year = {2003}
month = {Oct}
}