Published September 2011 | Version v1
Miscellaneous

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)

Part of:
Proceedings of the Ninth International Conference on Nuclear Criticality Safety - ICNC 2011

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.