Pingxun ZHANG, Bin ZHANG, Yixue CHEN. Core neutron source generation method for nuclear reactor shielding calculation[J]. NUCLEAR TECHNIQUES, 2023, 46(5): 050603
- NUCLEAR TECHNIQUES
- Vol. 46, Issue 5, 050603 (2023)
Fig. 1. Neutron importance of core for the pressure vessel in the NUREG/CR-6115 model
Fig. 2. Flow chart of geometric grid source assignment
Fig. 3. Geometric grid source mapping method (a) Geometric grid segmentation, (b) Sub-grid source calculation, (c) Geometric grid source assignment
Fig. 4. Geometric diagram of the NUREG/CR-6115 benchmark model 1-Core baffle, 2-Core barrel, 3-Inner inlet water gap, 4-Thermal shield, 5-Reactor pressure vessel liner, 6-Air gap, 7-Pressure vessel insulation, 8-Biological shield liner
Fig. 5. Source distribution of the NUREG/CR-6115 model (a) Average source calculation algorithm, (b) Multi-weight source mesh mapping algorithm
Fig. 6. Neutron spectrum distribution on internal surface of pressure vessel (a) Axial peak location, (b) RPV lower weld location
Fig. 7. Axial-normalized relative power distribution of the NUREG/CR-6115 model
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Table 1. Root mean square (RMS) of the relative error for fast neutron fluence in reactor pressure vessel (E>1.0 MeV)
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Table 2. Influence of neutron source distribution
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