首页> 中文期刊> 《近代物理研究所和兰州重离子加速器实验室年报:英文版》 >5-18 Measurement of Leakage Neutron Spectra from Graphite Cylinders

5-18 Measurement of Leakage Neutron Spectra from Graphite Cylinders

         

摘要

Graphite is applied to many applications in the field of atomic energy. In the design of nuclear reactors, such as ADS, HTGRs and fusion reactors, graphite is among the primary candidate materials for a reflector zone to soften the neutron spectrum. Moreover, the accurate prediction of tritium breeding ratio and nuclear heating rate sets the necessity of using adequate nuclear data for carbon since they have strong influence on the feasibility of the overall design of fusion reactors.

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