TY - JOUR

T1 - JENDL-3.2 covariance file

AU - Shibata, Keiichi

AU - Hasegawa, Akira

AU - Iwamoto, Osamu

AU - Chiba, Satoshi

AU - Sugimoto, Masayoshi

AU - Odano, Naoteru

AU - Kawano, Toshihiko

AU - NakajimA, Yutaka

AU - Murata, Toru

AU - Matsunobu, Hiroyuki

AU - Oh, Youl Soo

AU - Yokoyama, Kenji

AU - Sugino, Kazuteru

AU - Ishikawa, Makoto

AU - Kosako, Kazuaki

AU - Yamano, Naoki

AU - Kanda, Yukinori

PY - 2002/8

Y1 - 2002/8

N2 - Covariances of neutron nuclear data have been estimated for 16 nuclides contained in JENDL-3.2. The physical quantities for which covariances are deduced are cross sections, resolved and unresolved resonance parameters, the first order Legendre-polynomial coefficients for the angular distribution of elastically scattered neutrons, and fission neutron spectra. As for 233.235238u and 239‘241Pu, covariances were obtained also for the average number of neutrons emitted in fission. Least-squares methods were applied to obtain the covariances of those cross sections which were based on experimental data. A simultaneous evaluation method yielded uncertainties in the fission cross sections of 23SU, 238U, 239Pu, 240Pu and 241Pu. Covariances of nuclear model calculations were determined from uncertainties in model parameters. The covariance file thus obtained is processed by a system which has been developed, and used for the adjustment of group cross sections.

AB - Covariances of neutron nuclear data have been estimated for 16 nuclides contained in JENDL-3.2. The physical quantities for which covariances are deduced are cross sections, resolved and unresolved resonance parameters, the first order Legendre-polynomial coefficients for the angular distribution of elastically scattered neutrons, and fission neutron spectra. As for 233.235238u and 239‘241Pu, covariances were obtained also for the average number of neutrons emitted in fission. Least-squares methods were applied to obtain the covariances of those cross sections which were based on experimental data. A simultaneous evaluation method yielded uncertainties in the fission cross sections of 23SU, 238U, 239Pu, 240Pu and 241Pu. Covariances of nuclear model calculations were determined from uncertainties in model parameters. The covariance file thus obtained is processed by a system which has been developed, and used for the adjustment of group cross sections.

KW - Covariance

KW - Cross section

KW - Fission neutron spectrum

KW - JENDL-3.2

KW - Legendre coefficient

KW - Resonance parameter

UR - http://www.scopus.com/inward/record.url?scp=85010505633&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=85010505633&partnerID=8YFLogxK

U2 - 10.1080/00223131.2002.10875034

DO - 10.1080/00223131.2002.10875034

M3 - Article

AN - SCOPUS:85010505633

VL - 39

SP - 40

EP - 43

JO - Journal of Nuclear Science and Technology

JF - Journal of Nuclear Science and Technology

SN - 0022-3131

ER -