2002
DOI: 10.3327/jnst.39.1125
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Japanese Evaluated Nuclear Data Library Version 3 Revision-3: JENDL-3.3.

Abstract: 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 mode… Show more

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Cited by 463 publications
(324 citation statements)
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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%
“…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%
“…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%
“…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%