Integral Test of JENDL-3.3 with Shielding Benchmarks

Yamano, Naoki; Ueki, Koichiro; Maekawa, Fujio; Konno, Chikara; Ichihara, Chihiro; Hoshiai, Yasutsugu; Matsumoto, Yoshihiro; Hasegawa, Akira

doi:10.1080/00223131.2002.10875230

Journal of Nuclear Science and Technology

2002

DOI: 10.1080/00223131.2002.10875230

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Integral Test of JENDL-3.3 with Shielding Benchmarks

Naoki Yamano

Koichiro Ueki

Fujio Maekawa

et al.

Abstract: established in Japanese Nuclear Data Committee (JNDC) was applied to the integral test for mediwn-heavy nuclei such as Alwninum, Sodium, Titanium, Vanadium, Chromiwn, Iron, Cobalt, Nickel, Copper, Niobium and TlHlgsten. Calculations were made based on a continuous-eneIgy Monte Carlo code MCNP4B/4C and multi-group discrete ordinates codes ANISN and OORT. The latest version ofNJOY99 was employed to generate cross-section libraries for these transport codes. Calculations with JENDL-3.2, ENDFIB-Vl, FENDL-I and FEN… Show more

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Cited by 4 publications

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Evaluation of Neutron Nuclear Data for Sodium-23

Shibata

2002

Journal of Nuclear Science and Technology

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Neutron nuclear data of 23 Na have been evaluated in the neutron energy region up to 20 MeV. Evaluated are the elastic and inelastic scattering, capture, (n, 2n), (n, p), (n, α), (n, np), (n, nα) reaction and γ -ray production cross sections, and the angular and energy distributions of neutrons and γ -rays. The evaluation is mainly based on nuclear model calculations. The pre-equilibrium and direct-reaction processes were taken into account in addition to the compound process. The evaluated data have been compiled into the latest version of JENDL, JENDL-3.3.

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Evaluation of Neutron Nuclear Data for Sodium-23

Shibata

2002

Journal of Nuclear Science and Technology

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Japanese Evaluated Nuclear Data Library Version 3 Revision-3: JENDL-3.3

Shibata

Kawano

Nakagawa

et al. 2002

Journal of Nuclear Science and Technology

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450

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Evaluation for JENDL-3.3 has been performed by considering the accumulated feedback information and various benchmark tests of the previous library JENDL-3.2. The major problems of the JENDL-3.2 data were solved by the new library: overestimation of criticality values for thermal fission reactors was improved by the modifications of fission cross sections and fission neutron spectra for 235 U; incorrect energy distributions of secondary neutrons from important heavy nuclides were replaced with statistical model calculations; the inconsistency between elemental and isotopic evaluations was removed for medium-heavy nuclides. Moreover, covariance data were provided for 20 nuclides. The reliability of JENDL-3.3 was investigated by the benchmark analyses on reactor and shielding performances. The results of the analyses indicate that JENDL-3.3 predicts various reactor and shielding characteristics better than JENDL-3.2.

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Integrated nuclear data utilisation system for innovative reactors

Yamano

Hasegawa

Katō

et al. 2005

Radiation Protection Dosimetry

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A five-year research and development project on an integrated nuclear data utilisation system was initiated in 2002, for developing innovative nuclear energy systems such as accelerator-driven systems. The integrated nuclear data utilisation system will be constructed as a modular code system, which consists of two sub-systems: the nuclear data search and plotting sub-system, and the nuclear data processing and utilisation sub-system. The system will be operated with a graphical user interface in order to enable easy utilisation through the Internet by both nuclear design engineers and nuclear data evaluators. This paper presents an overview of the integrated nuclear data utilisation system, describes the development of a prototype system to examine the operability of the user interface and discusses specifications of the two sub-systems.

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Integral Test of JENDL-3.3 with Shielding Benchmarks

Cited by 4 publications

References 7 publications

Evaluation of Neutron Nuclear Data for Sodium-23

Evaluation of Neutron Nuclear Data for Sodium-23

Japanese Evaluated Nuclear Data Library Version 3 Revision-3: JENDL-3.3

Integrated nuclear data utilisation system for innovative reactors

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