Status of JENDL High Energy File

Watanabe, Yukinobu; Kosako, Kazuaki; Kunieda, S.; Chiba, Satoshi; Fujimoto, R.; Harada, Hideo; Kawai, Masayoshi; Maekawa, Fujio; Murata, Tōru; Nakashima, Hiroshi; Niita, Koji; Shigyo, Nobuhiro; Shimakawa, Satoshi; Yamano, Naoki; Fukahori, Tokio

doi:10.3938/jkps.59.1040

Cited by 86 publications

(39 citation statements)

References 13 publications

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“…The calculation was performed using the PHITS [9] code and various intranuclear cascade models, namely, Bertini, JAM, and INCL-4.6 [10], coupled with the statistical decay model of GEM [11]. The present experimental results were compared with the evaluation data of JENDL High Energy File 2007 (JENDL/HE-2007) [12] and with ENDF/HE-VI [13] for carbon. Figure 1 shows a comparison of the Al(p,x) 7 Be reaction.…”

Section: Calculation and Evaluated Datamentioning

confidence: 99%

Measurement of aluminum activation cross section and gas production cross section for 0.4 and 3-GeV protons

et al. 2017

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Abstract. To estimate the lifetime and the radiation dose of the proton beam window used in the spallation neutron source at J-PARC, it is necessary to understand the accuracy of the production cross section of 3-GeV protons. To obtain data on aluminum, the reaction cross section of aluminum was measured at the entrance of the beam dump placed in the 3-GeV proton synchrotron. Owing to the use of well-calibrated current transformers and a well-collimated beam, the present data has good accuracy. After irradiation, the cross sections of Al(p,x) 7 Be, Al(p,x) 22 Na-22 and Al(p,x) 24 Na were obtained by gamma-ray spectroscopy using a Ge detector. It was found that the evaluated data of JENDL/HE-2007 agree well with the current experimental data, whereas intra-nuclear cascade models (Bertini, INCL-4.6, and JAM) with the GEM statistical decay model underestimate by about 30% in general. Moreover, gas production, such as T and He, and the cross sections were measured for carbon, which was utilized as the muon production target in J-PARC. The experiment was performed with 3-GeV proton having beam power of 0.5 MW, and the gasses emitted in the process were observed using a quadrupole mass spectrometer in the vacuum line for beam transport to the mercury target. It was found that the JENDL/HE-2007 data agree well with the present experimental data.

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Section: Calculation and Evaluated Datamentioning

confidence: 99%

Measurement of aluminum activation cross section and gas production cross section for 0.4 and 3-GeV protons

et al. 2017

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“…Figure 4 shows the comparison of the neutron spectra measured and calculated for the TIARA benchmark experiment with the 43 MeV p-Li neutron source through iron, where the libraries used include LA150 [12] and JENDL/HE-2007 a [13]. As the shield thickness increases, LA150, which was used for previous IFMIF nuclear analyses, significantly overestimates the neutron flux.…”

Section: Tiara Transmission Benchmark Experimentsmentioning

confidence: 99%

Analyses of shielding benchmark experiments using FENDL-3 cross-section data starter library for ITER and IFMIF applications

Kondo

Fischer

Pereslavtsev

et al. 2014

Progress in Nuclear Science and Technology

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Recently IAEA has been conducting a coordinated research project to update the FENDL-2.1 nuclear data library to FENDL-3. In the present study, FENDL-3, Starter Library, Release 4 (FENDL-3/SLIB4) has been extensively tested through analysis of many fusion relevant benchmark problems. FENDL-3/SLIB4 gives better results for the FNG ITER shielding benchmark and the tungsten benchmark experiments than the previous FENDL-2.1. As for the shielding benchmark in the neutron energy range above 20 MeV, the TIARA transmission experiments through iron and concrete using p-Li quasi-monoenergetic neutron source have been analyzed. FENDL-3/SLIB4 provides satisfactory results for the TIARA shielding benchmark through iron. For concrete, however, some discrepancy was found. The present analysis suggests importance of 16 O data in the neutron energy range above 20 MeV for shielding calculations through concrete.

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“…The (2) where the first term Q + (ZA, ξ i − 1 , E) indicates a contribution of the particle-hole creations on the same nucleus at the same excitation energy E, and the second term, which is added in MPEM, is due to residual composite nucleus production by emitting a particle x; x would be one of proton, neutron, deuteron, triton, 3 He, or α-particle.…”

Section: Multi-particle Emission Exciton Modelmentioning

confidence: 99%

“…A special purpose file for high energy nuclear data was released as JENDL High Energy File 2004 (JENDL/HE-2004) for 66 nuclides [2] in 2004. Its updated version JENDL/HE-2007 [3], which included 107 nuclides, was released in 2007. They contained cross sections for neutron-and proton-induced reactions up to 3 GeV.…”

Section: Introductionmentioning

confidence: 99%

Extension of a nuclear reaction calculation code CCONE toward higher incident energies — multiple preequilibrium emission, and spectrum in laboratory system

Iwamoto

2013

Journal of Nuclear Science and Technology

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A nuclear reaction calculation code CCONE, which was developed for nuclear data evaluation for JENDL/AC-2008 and JENDL-4, has been upgraded to improve the prediction accuracy for calculated cross sections at nucleon incident energies higher than 20 MeV. Multiple particle emission, in which nucleons and complex particles up to α-particle are involved, from pre-equilibrium reaction process was implemented based on the sequential-decay calculations for all produced exciton states within the framework of the two-component exciton model. The effect of velocity-change of particle-emitting nuclei on the multiple emission in preequilibrium and compound processes, which was not included in the previous evaluations, was taken into account to obtain spectra in the laboratory system using an average velocity approximation for each composite/compound nucleus. Calculated nucleon emission spectra at nucleon incident energies from 20 to 200 MeV were compared with experimental and evaluated data for the proton-and neutroninduced reactions on 27 Al. The present results are in good agreement with experimental data. It was found that their predictions were better than those of JENDL/HE-2007 especially for low emission energies at high incident energies. Keywords: nuclear reaction; cross section; energy spectrum; preequilibrium process; exciton model; multi-particle emission; cluster emission; nuclear data IntroductionThe latest version of Japanese Evaluated Nuclear Data Library, JENDL-4.0 [1], was released in 2010. It included the cross sections for neutron-induced reactions below 20 MeV mainly for nuclear energy applications. At Nuclear Data Center, Japan Atomic Energy Agency(JAEA), it was planned to place emphasis on higher energy data after the release of JENDL-4.0. A special purpose file for high energy nuclear data was re- . The CCONE code uses modern nuclear reaction modelings and parametrizations integrating direct, preequilibrium and compound reactions and also has large

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Status of JENDL High Energy File

Cited by 86 publications

References 13 publications

Measurement of aluminum activation cross section and gas production cross section for 0.4 and 3-GeV protons

Measurement of aluminum activation cross section and gas production cross section for 0.4 and 3-GeV protons

Analyses of shielding benchmark experiments using FENDL-3 cross-section data starter library for ITER and IFMIF applications

Extension of a nuclear reaction calculation code CCONE toward higher incident energies — multiple preequilibrium emission, and spectrum in laboratory system

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