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:10.1080/18811248.2002.9715303

Cited by 446 publications

(60 citation statements)

References 62 publications

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“…The performance of the radiation shield has been evaluated by Monte-Carlo neutron and gamma-ray transport calculations using the MCNP5 code [11] and the JENDL-3.3 nuclear data library [12]. The calculation geometry was a simple torus as shown in Fig.…”

Section: Neutronics Calculationsmentioning

confidence: 99%

Design studies on three-dimensional issues for liquid blanket systems in helical reactor FFHR

Tanaka

Sagara

Goto

et al. 2012

Fusion Engineering and Design

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Section: Neutronics Calculationsmentioning

confidence: 99%

Design studies on three-dimensional issues for liquid blanket systems in helical reactor FFHR

Tanaka

Sagara

Goto

et al. 2012

Fusion Engineering and Design

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“…The nuclear data used for calculations in CFNB code is from JENDL3.3 [10], 300˚K files. The code has been tested in good agreement with results obtained from Monte Carlo code MCNP-5.…”

Section: Calculation Of Neutron Filtered Spectramentioning

confidence: 99%

Development of 24 and 59 keV Filtered Neutron Beams for Neutron Capture Experiments at Dalat Research Reactor

Tan¹,

Hoa²,

Anh³

2014

WJNST

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External filtered neutron beams have been developed at the horizontal radial channels No. 4 of Dalat research reactor. In the material composition of the neutron filters, the primary material components of Iron, Aluminum, Nickel and Vanadium are used to obtain the mono-energetic neutron beams of 24 and 59 keV, with low level of Gamma and slow neutron background. A computer code and Monte-Carlo simulation technique were applied to optimize the filter configurations and to deduce the neutron energy distributions in the filtered beams. A hydrogen-filled proton recoil detector and the activation method with Gold foils were used to measure the neutron energy spectrum and flux of each beam at sample position. The results of experimental neutron fluxes are 6.1 × 10 5 and 5.3 × 10 5 n/cm 2 /s for 24 and 59 keV beams, respectively.

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“…The burn-up calculation software, ORIGEN 2.2 (10) , and the nuclear cross section libraries (13) for ORIGEN 2 based on JENDL 3.3 (11) were used to calculate decay heat of fuel assemblies.…”

Section: Prediction Of Decay Heatmentioning

confidence: 99%

“…In another study, Yanagi et al (9) also carried out three-dimensional (3D) thermal hydraulic calculations of the SFP water during the shutdown of cooling systems using FLUENT6.3.26. In those calculations, they made and used a database for decay heat of spent fuel assemblies, which was calculated for several fuel types using the burn-up calculation software ORIGEN 2.2 (10) and the nuclear physics library JENDL3.3 (11) . However, 3D calculations require a long computing time.…”

Section: Introductionmentioning

confidence: 99%

One-Region Model Predicting Water Temperature and Level in a Spent Fuel Pit during Loss of All AC Power Supplies

Yanagi¹,

Murase²

2013

JPES

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A prediction system with a one-region model was developed to predict water temperature in a spent fuel pit (SFP) after the shutdown of its cooling systems based on three-dimensional (3D) thermal hydraulic behavior calculated by using the CFD software, FLUENT 6.3.26. The system was extended to calculate the water level in the SFP during loss of all AC power supplies. In the prediction system, decay heat calculated by using the burn-up calculation software, ORIGEN 2.2, and the previously proposed correlation for evaporation heat fluxes from the water surface to air were used. Predicted results were compared with 3D calculations and measured temperatures for the shutdown of cooling systems and with the water temperature and level measured in SFPs at the Fukushima Daiichi Nuclear Power Station for loss of all AC power supplies. As a result, the predicted temperatures were found to agree well with the 3D calculations and it was confirmed that ORIGEN 2.2 well predicted decay heat for fuel assemblies with large decay heat which had been taken relatively recently from the shutdown reactor core. However, it was shown that decay heat predicted by ORIGEN 2.2 was overestimated for longtime cooled fuel assemblies with small decay heat and the previously proposed evaporation heat flux correlation overestimated the water temperature in the SFP, too.

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

Cited by 446 publications

References 62 publications

Design studies on three-dimensional issues for liquid blanket systems in helical reactor FFHR

Design studies on three-dimensional issues for liquid blanket systems in helical reactor FFHR

Development of 24 and 59 keV Filtered Neutron Beams for Neutron Capture Experiments at Dalat Research Reactor

One-Region Model Predicting Water Temperature and Level in a Spent Fuel Pit during Loss of All AC Power Supplies

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