Improvements to MONK and MCBEND enabling coupling and the use of MONK calculated isotopic compositions in shielding and criticality - 7-20
- 1. Serco Technical Consulting Services, Kimmeridge House, Dorset Green Technology Park, Winfrith Newburgh, Dorchester, Dorset DT2 8ZB (United Kingdom)
Description
Isotopic composition through time can be derived for 3D reactor core configurations using the Monte Carlo Criticality and Reactor Physics code MONK. MONK can be coupled to thermal-hydraulics (TH) codes (e.g. RELAP5) to model temperature feedback and coupled to the Monte Carlo radiation transport code MCBEND for onward neutron and/or gamma calculations. MONK derived isotopic compositions can be directly and automatically transferred to another MONK or MCBEND model for either subsequent: -) burn-up steps or branching calculations with MONK using the same 3D whole core model; or -) shielding calculations with the compositions transferred to MCBEND utilised as elemental compositions of reactor components or fuels (for example in the case of a fuel flask or waste storage facility); or -) criticality calculations with the compositions transferred to another MONK model. Results from a typical whole core PWR calculation with MONK are presented demonstrating MONK TH code coupling and generating burnt-up isotopic compositions. The compositions from three PWR fuel assemblies were automatically transferred to separate MCBEND and MONK models of a fictitious spent nuclear fuel facility performing shielding and criticality calculations respectively. Results are presented to demonstrate the reactivity differences and how burn-up credit may be used. An innovative scheme for speeding up MONK and improving resolution of MONK burn-up/TH meshes utilising parallel computing architecture is described. This will enable refinement of isotopic composition variations even further. The parallelization scheme utilises a novel domain decomposition method, enables optimisation for user controlled calculation speed adjustment and has the potential for adaptive meshing. (authors)
Additional details
Publishing Information
- Imprint Title
- Proceedings of the Ninth International Conference on Nuclear Criticality Safety - ICNC 2011
- Imprint Pagination
- 1726 p.
- Journal Page Range
- 12 p.
- Report number
- INIS-XN--22-ICNC-2011
Conference
- Title
- International conference on nuclear criticality
- Acronym
- ICNC 2011
- Dates
- 19-22 Sep 2011
- Place
- Edinburgh (United Kingdom)
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- France
- INIS RN
- 53066775
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BURNUP; COMPUTERIZED SIMULATION; CRITICALITY; ISOTOPE RATIO; M CODES; NEUTRON FLUX; PWR TYPE REACTORS; SHIELDING; SPATIAL DISTRIBUTION
- Descriptors DEC
- COMPUTER CODES; DIMENSIONLESS NUMBERS; DISTRIBUTION; ENRICHED URANIUM REACTORS; POWER REACTORS; RADIATION FLUX; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 4 refs.