NUCLEAR TECHNIQUES, Volume. 46, Issue 3, 030601(2023)
Development and verification of a neutronics-thermal hydraulics coupling code with unstructured meshes neutron transport model
Fig. 1. Flowchart of the transient calculations with SCM in MORPHY
Fig. 3. The coupling method in MORPHY (a) OSSI method, (b) FPI method
Fig. 6. Layout of the Dodds problem (a) Material layout, (b) Radial mesh generation
Fig. 9. NEACRP benchmark problem relative power vs. time (a) NEACRP A1, (b) NEACRP A2, (c) NEACRP B1, (d) NEACRP B2
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Mingrui YANG, Qizheng SUN, Chixu LUO, Donghao HE, Xiaojing LIU, Tengfei ZHANG. Development and verification of a neutronics-thermal hydraulics coupling code with unstructured meshes neutron transport model[J]. NUCLEAR TECHNIQUES, 2023, 46(3): 030601
Category: Research Articles
Received: Aug. 19, 2022
Accepted: --
Published Online: Apr. 17, 2023
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