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Journal Articles

Nuclear heating and damage data in JENDL-5 neutron ACE library

Konno, Chikara

JAEA-Conf 2024-002, p.80 - 85, 2024/11

The official ACE files of JENDL-5 were released in December, 2022. The neutron ACE file of JENDL-5 was mainly produced with the FRENDY code, while the data on nuclear heating and damage (heating number, damage production energy) were done with the NJOY2016.65 code modified for JENDL-5. This presentation explains the modified points of NJOY2016.65 and the data on nuclear heating and damage in the neutron ACE file of JENDL-5.

Journal Articles

Overview and future of JENDL-5

Iwamoto, Osamu

JAEA-Conf 2024-002, p.41 - 46, 2024/11

Journal Articles

Evaluation of photonuclear reaction cross-section data for $$^{209}$$Bi at 13 and 17 MeV photon energies

Nguyen, T. T. H.*; Iwamoto, Nobuyuki; Sanami, Toshiya*

JAEA-Conf 2024-002, p.139 - 143, 2024/11

Journal Articles

Measurement of the spallation neutron spectrum by unfolding at 180$$^{circ}$$ from 3-GeV protons and $$^{nat}$$Hg with the $$^{209}$$Bi(n,xn) reactions

Sugihara, Kenta*; Meigo, Shinichiro; Iwamoto, Hiroki; Maekawa, Fujio

JAEA-Conf 2024-002, p.162 - 167, 2024/11

A neutron energy spectrum is important for shielding design at an Accelerator-Driven System facility (1.5-GeV p + Lead Bismuth Eutectic). A similar spectrum can be obtained at J-PARC (3-GeV proton + $$^{nat}$$Hg). To check the validity of the unfolding, the unfolding with the $$^{209}$$Bi(n,xn) reactions and the response functions (JENDL/HE-2007 and TALYS) was applied. In our poster, we present the derivation of the spectrum and comparison with the spectrum with a Time-of-Flight technique.

Journal Articles

Relationship with JENDL and expectations for possibilities of opening up nuclear data

Fukahori, Tokio

JAEA-Conf 2024-002, p.6 - 11, 2024/11

The author has been keeping relationship with Japanese Evaluated Nuclear Data Library for around 38 years. During this period, he has been contributing code developments, for example, Preequilibrium Nuclear Reaction Calculation Code (ALICE-F) and Particle and Heavy Ion Transport Code System (PHITS). The author has also been assisting for EXFOR activities and promoting Evaluated Nuclear Data Processing Code (FRENDY) and Multiphase Multicomponent Detailed Thermal Fluid Analysis Code (JUPITER). In this paper, introduced are the outline of the author's works. Also reported are the author's perspective and challenge for the future form of nuclear data.

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