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Neutron Streaming through an Iron Duct: Comparison of Measured and Calculated Neutron and gamma-ray Energy Spectra Using Monte Carlo MORSE and MCNP Codes. A Benchmark Experiment Proposal.

机译：中子流通过铁管：使用蒙特卡罗mORsE和mCNp代码比较测量和计算的中子和伽马射线能谱。基准实验提案。

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The shielding problem for a fusion reactor could, in principle, be similar to the fission reactor problem solved thirty years ago. Nevertheless, the large difference in the energy of neutrons (14 MeV for fusion, about 1 MeV for fission) requires, in connection with the shield design for a fusion reactor, improvement in the present calculation methods and key experiments in order to gain confidence in these calculations. This report presents the proposal of a neutron streaming experiment, to be used as a benchmark to test neutron code calculation. As measured by R.T. Santoro, neutron and gamma-ray energy spectra, resulting from the streaming of 14 MeV neutrons through a 0.3 m/diameter iron duct, are compared with spectra calculated by the use of 3-D Monte Carlo MORSE and MCNP codes.

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Batistoni, P.; Bertalot, L.; Martone, M.; Pillon, M.;
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年度 1985
页码 1-28
总页数 28
原文格式 PDF
正文语种 eng
中图分类工业技术;
关键词
Thermonuclear Reactors; Benchmarks; Biological Shielding; Calculation Methods; Comparative Evaluations; Gamma Spectra; M Codes; MeV Range 10-100; Monte Carlo Method; Neutron Spectra; Radiation Streaming; Neutron transport; Foreign technology; ERDA/654001; ERDA/700201;

机译：热核反应堆;基准;生物屏蔽;计算方法;比较评价;γ光谱; m代码; meV范围10-100;蒙特卡罗方法;中子光谱;辐射流;中子传输;国外技术; ERDa / 654001; ERDa / 700201;

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Neutron Streaming through an Iron Duct: Comparison of Measured and Calculated Neutron and gamma-ray Energy Spectra Using Monte Carlo MORSE and MCNP Codes. A Benchmark Experiment Proposal.

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