Development of a new convergence criterion for Monte Carlo simulation with thermal-hydraulics feedback
Creators
- 1. Department of Nuclear, Plasma and Radiological Engineering, University of Illinois at Urbana-Champaign, Urbana, IL (United States)
Description
Coupled multi-physics approach plays an important role in improving computational accuracy. Compared with deterministic neutronics codes, Monte Carlo codes have the advantage of higher resolution level. In the present paper, a three-dimensional continuous-energy Monte Carlo reactor physics burnup calculation code, Serpent, is coupled with thermal-hydraulics safety analysis code, RELAP5. A new convergence criterion for the coupled simulation is developed based on the statistical uncertainty in power distribution in Monte Carlo code, rather than an arbitrarily chosen criterion in previous research. The coupled simulation is based on the OECD-NEA/NRC PWR MOX-UO2 Core Transient Benchmark. The convergence criterion of normalized axial power distribution is tested on both UO2 and MOX single assembly models. Compared with previously implemented convergence criteria based on temperature, eigenvalue or flux (or power), it takes into account both the local and global convergence. It does not use a pre-set tolerance limit and is decided by the statistical accuracy of the Monte Carlo code itself. This new convergence criterion is shown to be stable, more stringent and direct, equally convenient to use but may need a few more steps to converge. (author)
Files
Additional details
Identifiers
Publishing Information
- Imprint Title
- Proceedings of the international conference on physics of reactors (PHYSOR2014)
- Imprint Pagination
- 5489 p.
- Journal Page Range
- 14 p.
- Report number
- JAEA-Conf--2014-003
Conference
- Title
- International conference on physics of reactors
- Acronym
- PHYSOR2014
- Dates
- 28 Sep - 3 Oct 2014
- Place
- Kyoto (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 47042626
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; CONVERGENCE; FEEDBACK; ITERATIVE METHODS; MIXED OXIDE FUELS; MONTE CARLO METHOD; NEUTRON TRANSPORT THEORY; POWER DISTRIBUTION; PWR TYPE REACTORS; REACTOR CORES; THERMAL HYDRAULICS; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; CALCULATION METHODS; CHALCOGENIDES; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FLUID MECHANICS; FUELS; HYDRAULICS; MATERIALS; MECHANICS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SIMULATION; SOLID FUELS; THERMAL REACTORS; TRANSPORT THEORY; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Available as CD-ROM Data in PDF format, Folder Name: PAPERS, Paper ID: a11_1101864.pdf; 14 refs., 11 figs., 2 tabs.