Neutron Nuclear Data Evaluation of Cesium Isotopes for JENDL-4.0

Iwamoto, Nobuyuki

doi:10.1080/18811248.2011.9711812

Cited by 8 publications

(5 citation statements)

References 46 publications

(91 reference statements)

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“…Recently, Reimer et al [24] measured the cross-sections in a wide energy range of [8][9][10][11][12][13][14][15][16][17][18][19][20] MeV. The present result as well as ENDF/B-VII.0 and JEFF-3.1.1 reasonably reproduces their data.…”

Section: (N P) Reaction Cross-sectionsupporting

confidence: 80%

“…The lower energy limit presently assumed will be replaced by an up-to-date upper limit of resolved resonance region, when the results of this work are compiled into an ENDF-formatted file [9]. The theoretical models used to calculate the reaction cross-sections were almost the same as those in the previous evaluation of neutron nuclear data for Zn [10] and Cs [11] isotopes. However, since there were a few modifications for the present work, the current setup is described in this section.…”

Section: Evaluation Methodsmentioning

confidence: 77%

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Evaluation of neutron nuclear data for Technetium-99

Iwamoto

2012

Journal of Nuclear Science and Technology

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Neutron nuclear data of 99 Tc was evaluated, considering cross-sections and spectra provided from recent experiments. The evaluation was made in the incident neutron energy range from 1 keV to 20 MeV, using the optical model and nuclear reaction models. The optical model calculation based on the coupledchannels method was performed for the interaction of neutrons with 99 Tc, and potential parameters appropriately chosen reasonably explain the measured data of total cross-section. The cross-section of inelastic scattering, capture, (n, 2n), (n, p), (n, a) and (n, n 0 a) reactions, and g-ray emission spectra were calculated on the basis of statistical model with preequilibrium and direct components, and they were compared with available experimental data. It is found that the presently evaluated cross-sections and g-ray emission spectra well reproduce those experimental values and that there is a large discrepancy among the present result and evaluated data for neutron emission spectra. The obtained capture crosssection increases at the energies below 1 MeV, relative to that in JENDL-4.0. This makes the transmutation efficiency of 99 Tc into stable 100 Ru by accelerator driven system enhanced. The production cross-section of 99 Mo important for the medical use of nuclear diagnostics reduces by 5-30% at the energies above 12 MeV, compared with JENDL-4.0.

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Section: (N P) Reaction Cross-sectionsupporting

confidence: 80%

Section: Evaluation Methodsmentioning

confidence: 77%

Evaluation of neutron nuclear data for Technetium-99

Iwamoto

2012

Journal of Nuclear Science and Technology

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“…The details of some evaluations are given elsewhere. [80,81,82,83,84,85,86,87,88,89] The data on Zn were newly evaluated [80]. The RRPs of 64,66−68 Zn were mainly based on the data measured at ORNL.…”

Section: Jendl-40mentioning

confidence: 99%

JENDL: Nuclear databases for science and technology

Shibata

2013

Journal of Nuclear Science and Technology

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It is exactly 50 years since the Japanese Nuclear Data Committee was founded both in the Atomic Energy Society of Japan and in the former Japan Atomic Energy Research Institute. The committee promoted the development of Japan's own evaluated nuclear data libraries. As a result, we managed to produce a series of Japanese Evaluated Nuclear Data Libraries (JENDLs) to be used in various fields for science and technology. The libraries are categorized into general-purpose and special-purpose ones. The generalpurpose libraries have been updated periodically by considering the latest knowledge on experimental and theoretical nuclear physics that was available at the time of the updates. On the other hand, the specialpurpose libraries have been issued in order to meet the needs for particular application fields. This paper reviews the research and development for those libraries.

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“…An innovative concept for a passive reactor shutdown system, so called self-actuated shutdown system (SASS), is inevitably required for the inherent safety in nuclear reactor, which is designed with the totally different concept from the usual reactor shutdown system.As the passive shutdown system, the SASS using Curie point electromagnet (CPEM) has been developed in several countries [1,2]. In this system, the control rod is held by the electromagnetic force of the CPEM.…”

Section: Introductionmentioning

confidence: 99%

Simulation of Proton Irradiation Damage for Fe-Ni Magnetic Alloy

Cao

Yang

2012

AMR

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The Fe-Ni magnetic alloy irradiated by 10 MeV and 20 MeV protons were simulated by TRIM program. The energy loss and irradiation damage were calculated, and some important results were concluded. The average number of vacancies of the irradiation with 10 MeV and 20 MeV protons are 131.7 and 214.5. The damage rate of the Fe-Ni magnetic alloy irradiated with 10 MeV and 20 MeV protons are 2.278×10-6 dpa/s and 1.227×10-6 dpa/s. For the 1µA protons, in order to reach the radiation damage dose of 2 dpa, it will need 244 h and 453 h irradiated by 10 MeV and 20 MeV protons respectively.

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Neutron Nuclear Data Evaluation of Cesium Isotopes for JENDL-4.0

Cited by 8 publications

References 46 publications

Evaluation of neutron nuclear data for Technetium-99

Evaluation of neutron nuclear data for Technetium-99

JENDL: Nuclear databases for science and technology

Simulation of Proton Irradiation Damage for Fe-Ni Magnetic Alloy

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