Published June 2018
| Version v1
Miscellaneous
Acceleration of fission source convergence in the Serpent 2 Monte Carlo code using a response matrix based solution for the initial source distribution
Creators
- 1. VTT Technical Research Centre of Finland, Ltd., Kivimiehentie 3, Espoo 02044 (Finland)
Description
This paper presents a new response matrix based solver implemented in the Serpent 2 Monte Carlo code for the purpose of producing an improved initial guess to accelerate source convergence in criticality source simulations. The solver obtains coupling coefficients required for the response matrix solution from Monte Carlo simulations, and provides a spatial distribution that approximates the converged fission source. The implemented methodology is demonstrated by single-assembly and full-core PWR calculations. The results show that the improved initial guess leads to faster source convergence in terms of both inactive cycles and overall running time. (Author)
Availability note (English)
Available from the Instituto Nacional de Investigaciones Nucleares, Centro de Informacion y Documentacion, 52750 Ocoyoacac, Estado de Mexico (MX), e-mail: mclaudia.gonzalez@inin.gob.mxAdditional details
Publishing Information
- Publisher
- Sociedad Nuclear Mexicana
- Imprint Place
- Ciudad de Mexico (Mexico)
- Imprint Pagination
- 12 p.
Conference
- Title
- reactor physics paving the way towards more efficient systems
- Acronym
- PHYSOR 2018
- Dates
- 22-26 Apr 2018
- Place
- Cancun, Q. R. (Mexico)
INIS
- Country of Publication
- Mexico
- Country of Input or Organization
- Mexico
- INIS RN
- 50022026
- Subject category
- S97: MATHEMATICAL METHODS AND COMPUTING;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ACCELERATION; COMPUTERIZED SIMULATION; CONVERGENCE; COUPLING; CRITICALITY; FISSION; GEOMETRY; MATHEMATICAL SOLUTIONS; MATRICES; MONTE CARLO METHOD; PWR TYPE REACTORS; SPATIAL DISTRIBUTION
- Descriptors DEC
- CALCULATION METHODS; DISTRIBUTION; ENRICHED URANIUM REACTORS; MATHEMATICS; NUCLEAR REACTIONS; POWER REACTORS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS