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A half-century of radioisotope neutron sources in China
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作者 Cai Shanyu 《Engineering Sciences》 EI 2009年第4期22-34,共13页
Near 50 years history of the development of radioisotope neutron sources in China is briefly reviewed.The structure design,preparing technology and production status of routine neutron sources including 210Po-Be sourc... Near 50 years history of the development of radioisotope neutron sources in China is briefly reviewed.The structure design,preparing technology and production status of routine neutron sources including 210Po-Be sources,210Po mock fission sources,241Am-Be sources,238Pu-Be sources,252Cf spontaneous fission sources and other special-shape neutron sources are summarized.In addition,the prospects of development on radioisotope neutron source in China are predicted from the needs of nuclear power construction,oil well-logging,neutron moisture gauge and neutron brachytherapy. 展开更多
关键词 radioisotope neutron source α n source spontaneous fission source source core preparing source capsule sealing quality control oil well-logging neutron moisture gauge neutron brachytherapy
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Neutron Radiography System Collimator Design via Monte Carlo Calculation
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作者 H. Jafari M. Shahriari 《Journal of Energy and Power Engineering》 2011年第12期1168-1172,共5页
Neutron radiography uses the unique interaction probabilities of neutrons to create images of materials. This imaging technique is non-destructive. MCNP Monte Carlo Code has been used to design an optimized neutron ra... Neutron radiography uses the unique interaction probabilities of neutrons to create images of materials. This imaging technique is non-destructive. MCNP Monte Carlo Code has been used to design an optimized neutron radiography system that utilizes 241Am-Be neutron source. Many different arrangements have been simulated to obtain a neutron flux with higher amplitude and more uniform distribution in the collimator outlet, next to image plane. In the final arrangement the specifications of neutron filter, Gamma-ray shield and beam collimator has been determined. Simulations has been carried out for a 5Ci 241Am-Be neutron source. In this case 43.8 n/cm2s thermal neutron flux has been achieved at a distance of 35 cm from neutron source. 展开更多
关键词 241Am-Be radioisotope source neutron radiography Monte Carlo collimator.
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