Status of Deterministic Transport Code Development at UNIST
Creators
- 1. Ulsan National Institute of Science and Technology, Ulsan (Korea, Republic of)
Description
At the end of this work, case test results are presented for both PWR and VHTR system. The library generation process and resonance treatment method in the deterministic transport code in UNIST has been summarized. The code shows reasonable results of keff compared to Monte Carlo results for pin cell problems. Deterministic transport code has been developed at UNIST. The code uses the method of characteristics (MOC) for neutron transport analysis. The MOC can provide accurate numerical solutions when accurate multi-group cross section library is given. In this work, nuclear library generation process and implemented resonance treatment method are presented. The code can cover PWR and VHTR system. NJOY code system and RMET21 are used to generate self-shielded cross section and resonance parameter. Equivalence theory is adopted in the code as a resonance treatment method. Additionally, Doubly-heterogeneous (DH) self-shielding method is implemented in the code to consider double heterogeneity of fuel in VHTR
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS Fall meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [2 p.]
Conference
- Title
- 2013 Fall meeting of the KNS
- Dates
- 23-25 Oct 2013
- Place
- Kyungju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 45082125
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CROSS SECTIONS; MONTE CARLO METHOD; N CODES; NEUTRON TRANSPORT; PWR TYPE REACTORS; TRANSPORT; U CODES; VHTR REACTOR
- Descriptors DEC
- CALCULATION METHODS; COMPUTER CODES; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; NEUTRAL-PARTICLE TRANSPORT; POWER REACTORS; RADIATION TRANSPORT; REACTORS; RESEARCH AND TEST REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 7 refs, 3 figs, 1 tab