MONK10: A Monte Carlo code for criticality analysis

David Long, Simon Richards, Paul N. Smith, Christopher Baker, Adam Bird, Nigel Davies, Geoff Dobson, Tim Fry, David Hanlon, Ray Perry, Max Shepherd

Research output: Chapter in Book/Report/Conference proceedingConference contribution

12 Citations (Scopus)


The MONK® code, if we include its predecessor GEM, has now been in use for 50 years. It is a Monte Carlo code for nuclear criticality and reactor physics analyses which is used extensively in the UK nuclear industry and worldwide. In 2014 a major new version of the code, MONK10A, was released introducing many new features; these are described with example applications presented where appropriate. Experience with MONK9A models indicates that MONK10A has increased run-time performance for all cases and on average runs 2.4 times faster. New geometry options include the direct import of CAD generated models using the new IGES body, POLY body, TETMESH Hole and TETMESH Zone features. Example calculations for a selection of CAD import options are presented and compared with the intrinsic MONK geometry representation, with relative merits discussed. New Features are included to assist with the modeling of distributed parameters; such features include Unified Tally (UT), Action Tallies (AT) in UT and Shannon entropy. The latter is useful in assessing the convergence of distributed parameters, such as scalar neutron flux. As such it is an important tool in determining the appropriate point to stop settling and begin scoring stages in a Monte Carlo simulation. The utility of UT, AT-in-UT and Shannon entropy is demonstrated using calculations employing the new CAD import geometry options. Runtime Doppler broadening is included to allow accurate representation of temperature distributions within models. Example calculations which further demonstrate UT and AT-in-UT are presented for different bodies at different temperatures to evaluate the effects of temperature differences on k-effective and reaction rates. The MONK10A code was issued with a new set of continuous energy and group nuclear data libraries. These include JEFF3.1, JEFF3.1.1, JEFF 3.1.2, ENDF/B-VII.0 and CENDL 3.1 libraries. The inclusion of a range of libraries allows the user to evaluate the impact of different international nuclear data evaluations on their results and an example is provided to illustrate the differences that can arise from the use of different nuclear data evaluations. The code was also issued with a new version of the VisualWorkshop IDE to allow easy construction and editing of input decks, running of calculations and display of geometry and results. Examples are provided of the geometry and results display and showing how results can be superimposed upon the geometry.

Original languageEnglish
Title of host publicationICNC 2015 - International Conference on Nuclear Criticality Safety
PublisherAmerican Nuclear Society
Number of pages13
ISBN (Electronic)9780894487231
Publication statusPublished - 1 Jan 2015
Externally publishedYes
Event2015 International Conference on Nuclear Criticality Safety, ICNC 2015 - Charlotte, United States
Duration: 13 Sept 201517 Sept 2015


Conference2015 International Conference on Nuclear Criticality Safety, ICNC 2015
Country/TerritoryUnited States


  • CAD
  • Criticality
  • Distributed parameters
  • MONK
  • Nuclear data


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