Published September 2011 | Version v1
Miscellaneous

The answers code MONK - A new approach to scoring, tracking, modelling and visualisation

  • 1. Serco Technical Consulting Services, Kimmeridge House, Dorset Green Technology Park, Winfrith Newburgh, Dorchester, Dorset DT2 8ZB (United Kingdom)
  • 2. Sellafield Ltd, Hinton House, Risley, Warrington, Cheshire, WA3 6AS (United Kingdom)

Description

The Monte Carlo code MONK has a proven track record of application to the whole of the nuclear fuel cycle and is well-established in the UK criticality community. MONK is part of a continuing development programme comprising the code, nuclear data libraries, validation, guides, geometry model visualisation tools and productivity tools. This paper describes many developments that have been made or are being made to the MONK package, including: -) Enhancements to the geometry modelling capabilities such as CAD import using both IGES models and tetrahedral mesh models; -) Run-time Doppler broadening for the BINGO collision processor, to allow calculations to be performed at any temperature; -) Continuous-energy depletion to further enhance the depletion capabilities of the code in the Burnup Credit application area; -) Parallelization; -) Extensions to the parameter and formula input facilities to simplify model specification; -) Unified tally option to enable fluxes to be scored in user defined volumes by materials/energy groups and events to be scored in these user defined volumes by reaction type/material/nuclide/energy group; -) Updates to the BINGO continuous-energy nuclear data libraries including JEFF3.1, ENDF/B-VII and CENDL3.1; -) The Integrated Development Environment package Visual Workshop 2 allowing input data to be created and edited, geometries to be displayed and checked, and results displayed over the geometry; -) Productivity Tools - the on-going development of LaunchPad (within Visual Workshop), automatic output checking (MONKcheck), and a facility for launching MONK across a network of computers (CODEMORE). (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.

Conference

Title
9. International Conference on Nuclear Criticality Safety
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
53051866
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COMPUTERIZED SIMULATION; CRITICALITY; M CODES; MONTE CARLO METHOD; NEUTRON TRANSPORT; SPECIFICATIONS
Descriptors DEC
CALCULATION METHODS; COMPUTER CODES; NEUTRAL-PARTICLE TRANSPORT; RADIATION TRANSPORT; SIMULATION

Optional Information

Notes
4 refs.
Secondary number(s)
INIS-XN--22-ICNC-2011-3-04