Xuejun Jia

The high-energy multi-group HEST1.0 library based on ENDF/B-VII.0: development, verification and preliminary application

ENDF/B-VII.0, which was released by the USA Cross Section Evaluation Working Group (CSEWG) in December 2006, was demonstrated to perform much better than previous ENDF evaluations over a broad range of benchmark experiments. A high-energy (up to 150 MeV) multi-group library set named HEST1.0 with 253-neutron and 48-photon groups has been developed based on ENDF/B-VII.0 using the NJOY code. This paper provides a summary of the procedure to produce the library set and a detailed description of the verification of the multi-group library set by several shielding benchmark devices, in particular for high-energy neutron data. In addition, the first application of HEST1.0 to the shielding design of the China Spallation Neutron Source (CSNS) is demonstrated.

Target station status of China Spallation Neutron Source

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Preliminary shielding analysis in support of the CSNS target station shutter neutron beam stop design

The construction of China Spallation Neutron Source (CSNS) has been initiated in Dongguan, Guangdong, China. Thus a detailed radiation transport analysis of the shutter neutron beam stop is of vital importance. The analyses are performed using the coupled Monte Carlo and multi-dimensional discrete ordinates method. The target of calculations is to optimize the neutron beamline shielding design to guarantee personal safety and minimize cost. Successful elimination of the primary ray effects via the two-dimensional uncollided flux and the first collision source methodology is also illustrated. Two-dimensional dose distribution is calculated. The dose at the end of the neutron beam line is less than 2.5 μSv/h. The models have ensured that the doses received by the hall staff members are below the standard limit required.

Preliminary shielding analysis for the CSNS target station monolith

The construction of the China Spallation Neutron Source (CSNS) has been initiated at Dongguan, Guangdong, China. In spallation neutron sources the target station monolith is contaminated by a large number of fast neutrons whose energies can be as large as those of the protons of the proton beam directed towards the tungsten target. A detailed radiation transport analysis of the target station monolith is important for the construction of the CSNS. The analysis is performed using the coupled Monte Carlo and multi-dimensional discrete ordinates method. Successful elimination of the primary ray effects via the two-dimensional uncollided flux and first collision source methodology is also illustrated. The dose at the edge of the monolith is calculated. The results demonstrate that the doses received by the hall staff members are below the required standard limit.