Current status of the reactor physics code WIMS and recent developments. (April 2017)

• Record Type: Journal Article
• Authors: Lindley, B.A.; Hosking, J.G.; Smith, P.J.; Powney, D.J.; Tollit, B.S.; Newton, T.D.; Perry, R.; Ware, T.C.; Smith, P.N.
• Is Part Of: Annals of nuclear energy. Volume 102(2017:Apr.)
• Page Start: 148
• Page End: 157
• Publication Date: 2017-04
• Subjects: Nuclear energy -- Periodicals; Nuclear engineering -- Periodicals; 621.4805
• DOI: 10.1016/j.anucene.2016.09.013
• Languages: English
• ISSNs: 0306-4549

Abstract

Highlights: The current status of the WIMS reactor physics code is presented. Applications range from 2D lattice calculations up to 3D whole core geometries. Gamma transport and thermal-hydraulic feedback models added. Calculations methodologies described for several Gen II, III and IV reactor types. Abstract: The WIMS modular reactor physics code has been under continuous development for over fifty years. This paper discusses the current status of WIMS and recent developments, in particular developments to the resonance shielding methodology and 3D transport solvers. Traditionally, WIMS is used to perform 2D lattice calculations, typically to generate homogenized reactor physics parameters for a whole core code such as PANTHER. However, with increasing computational resources there has been a growing trend for performing transport calculations on larger problems, up to and including 3D full core models. To this end, a number of the WIMS modules have been parallelised to allow efficient performance for whole core calculations, and WIMS includes a 3D method of characteristics solver with reflective and once-through tracking methods, which can be used to analyse problems of varying size and complexity. A time-dependent flux solver has been incorporated and thermal-hydraulic modelling capability is also being added to allow steady-state and transient coupled calculations to be performed. WIMS has been validated against a range of experimental data and other codes, in particular for water and graphite moderated thermal reactors. Future developments will include improved parallelization, enhancing the thermal-hydraulic feedback models and validating the WIMS/PANTHER code system for BWRs and fast reactors.