Continuous Energy COMET Solution of the VHTR Core
Creators
- 1. Georgia Institute of Technology, 770 State Street NW, Atlanta, GA 30332 0745 (United States)
Description
Recently, the hybrid stochastic deterministic coarse mesh radiation transport method COMET for whole core criticality calculations was extended to treat the energy variable continuously consistent with its treatment of the rest of the phase space variables. As a result, COMET now has continuous energy Monte Carlo accuracy but with formidable computational speed. In this paper, we present the continuous energy COMET solution to a stylized Very High Temperature Reactor (VHTR) benchmark problem in which all the heterogeneities that are of reactor physics importance are preserved. Because of its complex geometry and material distribution, this benchmark problem is challenging to solve with deterministic neutronic methods, even those based on transport theory. The eigenvalue and pin and fuel block averaged for all control rods inserted and fully withdrawn were compared to the corresponding values calculated by the continuous energy Monte Carlo code MCNP. It was found that the agreement between the two codes is excellent (0.8% 2.2%) except in the fuel pins next to the reflector blocks, where differences near 6% were observed. (author)
Additional details
Publishing Information
- Imprint Title
- 9th International Conference on High Temperature Reactor Technology (HTR2018)
- Imprint Pagination
- vp.
- Journal Page Range
- 6 p.
- Report number
- INIS-PL--23M0001
Conference
- Title
- 9. International Conference on High Temperature Reactor Technology
- Acronym
- HTR2018
- Dates
- 8-10 Oct 2018
- Place
- Warsaw (Poland)
INIS
- Country of Publication
- Poland
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 54064560
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCURACY; COMPARATIVE EVALUATIONS; CONTROL ELEMENTS; CRITICALITY; FEDERAL REPUBLIC OF GERMANY; FORSCHUNGSZENTRUM JUELICH; FUEL PINS; HTGR TYPE REACTORS; MONTE CARLO METHOD; NUCLEAR FUELS; REACTOR PHYSICS
- Descriptors DEC
- CALCULATION METHODS; DEVELOPED COUNTRIES; ENERGY SOURCES; EUROPE; EVALUATION; FUEL ELEMENTS; FUELS; GAS COOLED REACTORS; GERMAN FR ORGANIZATIONS; GRAPHITE MODERATED REACTORS; MATERIALS; NATIONAL ORGANIZATIONS; PHYSICS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; WESTERN EUROPE
Optional Information
- Notes
- Document from Juelich Preservation Project; 8 refs., 7 figs., 4 tabs.
- Secondary number(s)
- HTR2018--171