Review of simulation codes applicable to evaluation of high energy neutron dose

Sato, Tatsuhiko

Hoshasen, 31(4), p.313 - 318, 2005/10

http://ci.nii.ac.jp/naid/10016952728

Evaluation of high-energy neutron dose is one of the key issues in the shielding design of accelerator facilities and in the planning of long-term space missions. High-energy neutron transport simulation codes play an important role in the evaluation, since there is a large difficulty in the precise measurement of high-energy neutron doses. This paper reviews the Monte-Carlo simulation codes applicable to the purpose, and summarizes the requirements for the future development of the codes.

Study on response function of organic liquid scintillator for high-energy neutrons

Satoh, Daiki; Sato, Tatsuhiko; Endo, Akira; Yamaguchi, Yasuhiro; Takada, Masashi*; Ishibashi, Kenji*

AIP Conference Proceedings 769, p.1680 - 1683, 2005/05

https://doi.org/10.1063/1.1945332

Response function of liquid organic scintillators is essential to derive the accurate neutron spectrum. Experimental data above 100 MeV, however, are very scarce. The existing Monte Carlo codes, SCINFUL and CECIL, are often used for estimation of the response function instead of the experimental data. These codes are known to reproduce well the response function for incidences below 100 MeV. Unfortunately, the codes are not applicable to the calculation in the higher energy region. In order to determine the response functions above 100 MeV, a new Monte Carlo code, designated as SCINFUL-QMD, has been developed. In the comparison with the experimental data up to 800 MeV, the validation of SCINFUL-QMD was confirmed. The results of SCINFUL-QMD agreed with the experimental data better than those of other calculation codes.

Development of SCINFUL-CG code to calculate response functions of scintillatiors with various shapes used for neutron measurement

Endo, Akira; Kim, E.; Yamaguchi, Yasuhiro

JAERI-Data/Code 2001-027, 62 Pages, 2001/10

JAERI-Data-Code-2001-027.pdf:2.05MB

SCINFUL has been used to calculate response functions of organic scintillators for high-energy neutron spectroscopy. However, the applicability of SCINFUL is limited to the calculations for cylindrical NE213 and NE110 scintillators. In the present study, SCINFUL-CG was developed by introducing a geometry specifying function and high-energy neutron cross-section data into SCINFUL. The geometry package MARS-CG, the extended version of the CG (Combinatorial Geometry), was programmed into SCINFUL-CG to express various geometries of detectors. Neutron spectra in the regions specified by the CG can be evaluated by the track length estimator. The cross section data of silicon, oxygen and aluminum for neutron transport calculation were incorporated up to 100MeV using the data of LA150. Validity of SCINFUL-CG was examined by comparing calculated results with those by SCINFUL and MCNP and experimental data. SCINFUL-CG can be used for the designs of high-energy neutron spectrometers and neutron monitors using the organic scintillators. The present report is a user's manual of SCINFUL-CG.

Concept and neutron-field characteristics of ESNIT

Noda, Kenji; Oyama, Yukio; ; Maekawa, Hiroshi; Hishinuma, Akimichi

Journal of Nuclear Materials, 174, p.319 - 326, 1990/00

https://doi.org/10.1016/0022-3115(90)90244-H

no abstracts in English

Spectrum measurement for low-energy components of quasi-monoenergetic high-energy neutron field at TIARA

Masuda, Akihiko*; Matsumoto, Tetsuro*; Harano, Hideki*; Yoshitomi, Hiroshi; Tanimura, Yoshihiko; Shikaze, Yoshiaki; Kurashima, Satoshi; Seito, Hajime; Yoshizawa, Michio

no journal, , 

no abstracts in English