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Radiation Protection Dosimetry 2005 116(1-4):284-289; doi:10.1093/rpd/nci037
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© The Author 2005. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oxfordjournals.org

Comparison of thermal neutron distributions within shield materials obtained by experiments, SN and monte carlo code calculations

Yoshihiro Asano1,*, Takeshi Sugita2, Takenori Suzaki3 and Hideyuki Hirose3

1 Japan Atomic Energy Research Institute, SPring-8, Mikazuki-cho, Hyogo 679-5143, Japan
2 Science and System Laboratory, Ltd, 1342-6 Sumiyoshi, Tomobe-cho, Ibaragi 309-1716, Japan
3 Japan Atomic Energy Research Institute, Tokai Establishment, Tokai, Ibaragi, 319-1195, Japan

* Corresponding author: asano{at}spring8.or.jp

Benchmark experiments of thermal neutron distributions within the shield materials, graphite pile and pure water, were performed by using 252Cf fission neutrons and gold foil activation detectors, and, to these results, the estimates obtained by using the discrete ordinate code ANISN and the Monte Carlo code MCNP5 with two different cross-section libraries, ENDF/B-VI and the Japanese new version of JENDL-3.3, were compared. The results revealed that the MCNP5 calculations with the two libraries closely agree with the experiments and that there are slight differences between the MCNP5 and the ANISN calculations. The differences are caused mainly by the overestimation of the thermal neutron absorption cross sections constructed in NJOY99. The ANISN calculations with the modified absorption cross sections reproduced the results of the MCNP5 fairly well.


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