Integral Assessment of the Revised JENDL Dosimetry File

Kobayashi, Kazuyoshi; Iguchi, Tetsuo; Iwasaki, S.; Aoyama, Takafumi; Shimakawa, Satoshi; Ikeda, Yujiro; Odano, Naoteru; Sakurai, Kiyoshi; Shibata, Kozo; Nakagawa, Tsutomu; Nakazawa, Masaharu

doi:10.1520/stp13620s

Cited by 5 publications

(6 citation statements)

References 7 publications

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“…The incident neutron fluence was determined by the aluminum foil activation method at the outlet of the neutron beam. As the standard cross section for the 27 Al(n, ) reaction, 120.4 mb evaluated in JENDL Dosimetry File 99 11) was used. The neutron flux was supplementary monitored with a 238 U fission chamber at approximately 5 m downstream from the vacuum chamber during the measurement.…”

Section: Methodsmentioning

confidence: 99%

Measurement of Charged-Particle Emission Double-Differential Cross Section of Fluorine for 14.2MeV Neutrons

Kondo

Murata

Ochiai

et al. 2011

Journal of Nuclear Science and Technology

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We carried out detailed measurement of the double-differential cross sections of fluorine for the emissions of protons, deuterons, tritons, and -particles with 14.2 MeV incident neutrons. An improved charged-particle spectrometer with a pencil DT-neutron beam furnished at the FNS facility of the Japan Atomic Energy Agency enabled us to obtain precise data with a fine energy resolution over a wide energy range and an angular range from 15 to 150 . The present experiment is the first simultaneous measurement of the four different kinds of charged particles and provides useful data to establish a nuclear reaction model of fluorine as well as to confirm previous experimental data. Angular-differential cross sections for several discrete peaks corresponding to excited states of residual nuclei were extracted to discuss the reaction mechanism of charged-particle emission. The obtained data suggest that the charged-particle emission reaction of fluorine has a complicated mechanism in which there are contributions from the direct reaction, pre-equilibrium, and equilibrium processes. The obtained data were compared with the nuclear data evaluated in JENDL-3.3 and ENDF/B-VII.0. The results show large differences in the energy and angular distributions of emitted particles and the charged-particle production cross sections between the measured and evaluated data.

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Section: Methodsmentioning

confidence: 99%

Measurement of Charged-Particle Emission Double-Differential Cross Section of Fluorine for 14.2MeV Neutrons

Kondo

Murata

Ochiai

et al. 2011

Journal of Nuclear Science and Technology

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“…In the calculation, the cyclotron facility including material compositions, beam energy, beam current (beam losses), and beam radius (1.1 cm) on the X-course, were precisely modelled. Absorption cross-section data of 197 Au (n, γ) 198 Au based on the JENDL dosimetry file [13] was used to convert from the calculated neutron fluxes with PHITS-DCHAIN to the reaction rates, listed in Table 2. The statistical errors (uncertainties) of calculation results for neutron transport calculations were far lower than 10%.…”

Section: Calculation Resultsmentioning

confidence: 99%

Measurements and analyses of the distribution of the radioactivity induced by the secondary neutrons produced by 17-MeV protons in compact cyclotron facility

et al. 2017

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Abstract. Measurements of reaction rates by secondary neutrons produced from beam losses by 17-MeV protons are conducted at a compact cyclotron facility with the foil activation method. The experimentally obtained distribution of the reaction rates of 197 Au (n, γ) 198 Au on the concrete walls suggests that a target and an electrostatic deflector as machine components for beam extraction of the compact cyclotron are principal beam loss points. The measurements are compared with calculations by the Monte Carlo code: PHITS. The calculated results based on the beam losses are good agreements with the measured ones within 21%. In this compact cyclotron facility, exponential attenuations with the distance from the electrostatic deflector in the distributions of the measured reaction rates were observed, which was looser than that by the inverse square of distance.

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“…-JENDL-3.3 (ACE file : FSXLIB-J33 9) ) -JEFF-3.1 (ACE file : MCJEFF3.1NEA 10) ) -ENDF/B-VII.0 (ACE file : endf70 in MCNP Data 11) ) JENDL Dosimetry file 99 12) was adopted as the reaction cross section data for calculation of dosimetry reaction rates.…”

Section: Discussionmentioning

confidence: 99%

Benchmark Test of JENDL-4.0 Based on Integral Experiments at JAEA/FNS

Konno

Takakura

Wada³

2011

Progress in Nuclear Science and Technology

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The major revised version of Japanese Evaluated Nuclear Data Library (JENDL), JENDL-4.0, was released in May, 2010. As the benchmark test of JENDL-4.0 in the shielding and fusion neutronics fields, we analyzed many integral benchmark experiments (in-situ and Time-of-Flight (TOF) experiments) with DT neutrons at JAEA/FNS with the MCNP code and JENDL-4.0. The experiments with assemblies including beryllium, carbon, silicon, vanadium, copper, tungsten and lead, nuclear data of which were revised in JENDL-4.0, were selected for this benchmark test. As a result, it is demonstrated that JENDL-4.0 improves some problems pointed out in JENDL-3.3. JENDL-4.0 is comparable to ENDF/B-VII.0 and JEFF-3.1.

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Integral Assessment of the Revised JENDL Dosimetry File

Cited by 5 publications

References 7 publications

Measurement of Charged-Particle Emission Double-Differential Cross Section of Fluorine for 14.2MeV Neutrons

Measurement of Charged-Particle Emission Double-Differential Cross Section of Fluorine for 14.2MeV Neutrons

Measurements and analyses of the distribution of the radioactivity induced by the secondary neutrons produced by 17-MeV protons in compact cyclotron facility

Benchmark Test of JENDL-4.0 Based on Integral Experiments at JAEA/FNS

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