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Benchmark test of TRIPOLI-4 code through simple model calculation and analysis of fusion neutronics experiments at JAEA/FNS

Ota, Masayuki; Takakura, Kosuke; Ochiai, Kentaro; Sato, Satoshi; Konno, Chikara  

Three-dimensional Monte Carlo transport code is widely used in analyses of radiation protection and shielding, nuclear criticality safety, fission and fusion reactor design and nuclear instrumentation. The MCNP code is worldwide used as the standard code. The TRIPOLI code is adopted as one of ITER neutronics codes, but it is not always used worldwide, particularly in Japan. In this study we examined the basic performance of TRIPOLI through simple model calculations and analysis of iron neutronics experiments with DT neutrons at the Fusion Neutronics Source facility in Japan Atomic Energy Agency. Almost results by TRIPOLI are consistent with ones by MCNP. However, there is a difference between TRIPOLI and MCNP results in some calculations caused mainly by treatment with inelastic scattering data.

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Category:Nuclear Science & Technology

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