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

Shibata, Kozo; Kawano, Toshihiko; Nakagawa, Tsuneo; Iwamoto, Osamu; Katakura, J.; Fukahori, Tokio; Chiba, Satoshi; Hasegawa, Akira; Murata, Tōru; Matsunobu, Hiroyuki; Ohsawa, Takaaki; Nakajima, Yoshikazu; Yoshida, Tadashi; Zukeran, Atsushi; Kawai, Masayoshi; Baba, Mamoru; Itō, Makoto; Asami, Tetsuo; Watanabe, Takashi; Watanabe, Yukinobu; Igashira, M.; Yamamuro, Nobuhiro; Kitazawa, H.; Yamano, Naoki; Takano, Hideki

doi:10.3327/jnst.39.1125

Cited by 463 publications

(324 citation statements)

References 61 publications

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“…Model code calculations for nuclear reactions play a significant role in nuclear data evaluations in modern nuclear data libraries, such as ENDF, 2) JENDL, 3) and JEFF. 4) A complete set of evaluated nuclear data requires not only the reaction cross sections but also energy spectra of particle emission, -ray production cross sections, angular distributions of emitted particles, and so on.…”

Section: Introductionmentioning

confidence: 99%

Monte Carlo Simulation for Particle and γ-Ray Emissions in Statistical Hauser-Feshbach Model

Kawano

Talou

Chadwick

et al. 2010

Journal of Nuclear Science and Technology

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Monte Carlo simulations for particle and -ray emissions from a compound nucleus based on the Hauser-Feshbach statistical theory with pre-equilibrium emission are performed. The simulation yields reliable nuclear-reaction-wise energy spectra, or so-called exclusive spectra, for emitted neutrons and -rays, which are required in particle transport calculations for nuclear applications. The Monte Carlo method is applied to neutron-induced nuclear reactions on 56 Fe, and the results are compared with a traditional deterministic method. The neutron and -ray emission correlation is examined by gating on an 847 keV -ray that is produced by an inelastic scattering process. The partial -ray energy spectra for different -ray multiplicities are inferred using this Monte Carlo method. In addition, we investigate a correlation between two neutrons in the (n,2n) reaction.

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Section: Introductionmentioning

confidence: 99%

Monte Carlo Simulation for Particle and γ-Ray Emissions in Statistical Hauser-Feshbach Model

Kawano

Talou

Chadwick

et al. 2010

Journal of Nuclear Science and Technology

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“…22.2 This figure also shows typical spectra of hypothetical fuel debris of a BWR fuel pellet (3.7 wt.% 235 U, 27.5 GWd/t, 5-year-cooled), for comparison. Both spectra were calculated using a burn-up code, ORIGEN2 [9], and a Monte Carlo code, MVP2 [10], with a nuclear data library, JENDL-3.3 [11]. It can be seen in Fig.…”

Section: Critical Experiments On Criticality Safety For Fuel Debrismentioning

confidence: 99%

Modification of the STACY Critical Facility for Experimental Study on Fuel Debris Criticality Control

Sono

Tonoike

Izawa

et al. 2014

Nuclear Back-End and Transmutation Technology for Waste Disposal

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For the decommissioning of the Fukushima Daiichi Nuclear Power Stations, fuel debris involving molten structural materials should be retrieved from each reactor unit. The fuel debris, which is of uncertain chemical composition and physical state, needs to be treated with great care from the standpoint of criticality safety. For developing criticality control for the fuel debris, the Japan Atomic Energy Agency (JAEA) has been planning to modify the Static Experiment Critical Facility (STACY) and to pursue critical experiments on fuel debris. STACY, a facility using solution fuel, is to be converted into a thermal critical assembly using fuel rods and a light water moderator. A series of critical experiments will be conducted at the modified STACY using simulated fuel debris samples. The simulated fuel debris samples are to be manufactured by mixing uranium oxide and reactor structural materials with various chemical compositions. This report summarizes a facility development project for an experimental study on criticality control for fuel debris using the modified STACY and simulated fuel debris samples.

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“…The MCNP5 code [5] with neutron nuclear data library based on JENDL-3.3 [6] and photoatomic data library MCPLIB04 based on data from ENDF/B-VI release 8 [7] was used for the simulations. One dimensional slab arrangement of shielding material was adopted for the calculation model.…”

Section: Evaluation Of Shielding Performance By Monte Carlo Simulationmentioning

confidence: 99%

Development of high-performance gel-type radiation shielding material using polymer resin

Odano

Konnai

Asami

2014

Progress in Nuclear Science and Technology

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New gel-type shielding material, mainly consists of resin, lead powder and a boron compound, was developed. For simplification of the production process, new production method blending two types of liquid of base resin and a hardening accelerator was developed. To produce base resin, the crosslinking agent and the polymerization agent were blended with the thermosetting resin, first, and boric acid and lead were blended with the oligomerized component. Although the blended material is in gel condition immediately after blending, it has the feature hardened automatically without any processing. Radiation shielding performance of developed gel-type shielding material for neutron and gamma ray up to 25 cm in thickness were measured using standard sources of 252 Cf and 60 Co. It was found that new shielding material was able to reduce neutron dose rate half for that of ordinary concrete and shielding performance for gamma-ray was slightly good compared with that of ordinary concrete. Monte Carlo simulations were also carried out to confirm radiation shielding performance of newly developed gel-type shielding material for neutron and gamma ray up to 100 cm in thickness. From the experiments and simulations, it was shown that newly developed gel-type shielding material has excellent shielding performance compared with that of ordinary concrete, and can be used for compensated shield in the case of accident.

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

Cited by 463 publications

References 61 publications

Monte Carlo Simulation for Particle and γ-Ray Emissions in Statistical Hauser-Feshbach Model

Monte Carlo Simulation for Particle and γ-Ray Emissions in Statistical Hauser-Feshbach Model

Modification of the STACY Critical Facility for Experimental Study on Fuel Debris Criticality Control

Development of high-performance gel-type radiation shielding material using polymer resin

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