Open Access
| Issue |
EPJ Web Conf.
Volume 247, 2021
PHYSOR2020 – International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future
|
|
|---|---|---|
| Article Number | 06006 | |
| Number of page(s) | 10 | |
| Section | Advanced Modelling and Simulation | |
| DOI | https://doi.org/10.1051/epjconf/202124706006 | |
| Published online | 22 February 2021 | |
- B.A. Lindley, J.G. Hosking, P.J. Smith, D.J. Powney, B.S. Tollit, T.D. Newton, R. Perry, T.C. Ware, P.N. Smith, “Current status of the reactor physics code WIMS and recent developments,” Annals of Nuclear Energy, 102, pp 148-157 (2017). [Google Scholar]
- N.Z. Chom “KAIST/NurapT: Benchmark Problem 1A: MOX Fuel-Loaded Small PWR Core (MOX Fuel with Zoning,” http://nurapt.kaist.ac.kr/benchmark/ (2000). [Google Scholar]
- B. Kochunas, D. Jabaay, B. Collins, T. Downar, “Coupled Single Assembly Solution with COBRATF/MPACT (Problem 6),” CASL-U-2013-0280-000, CASL U.S Department of Energy (2013). [Google Scholar]
- F. Tantillo, S. Richards, A. Smethurst, D. Long, “INTEGRATION OF THE MONK MONTE CARLO NEUTRONICS CODE IN THE NURISM PLATFORM,” Proceedings of International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering (2019). [Google Scholar]
- D. Gaston, C. Permann, J. Peterson, A. Slaughter, D. Andrs, Y. Wang, M. Short, D. Perez, M. Tonks, J. Ortensi, L. Zou, R. Martineau, “Physics-base multiscale coupling for full core nuclear reactor simulation,” Annals of Nuclear Energy, 84, pp 45-54 (2015). [Google Scholar]
- J.G. Hosking, B.A. Lindley, P.J. Smith, “CACTUSOT: A 3D Method of Characteristics Solver in WIMS,” Proceedings of International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering (2017). [Google Scholar]
- U. Davies, B. Lindley, B. Tollit, E. Shwageraus, “Whole-core validation of the Superphenix reactor using WIMS11 and an investigation into a hybrid RZ-HEX SP3 calculation route,” Proceedings of International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering (2019). [Google Scholar]
- B. Tollit, A. Charles, A. Cox, K. Kohli, B. Lindley, G. Hosking, P.J. Smith, M. Dillistone, P.N. Smith, “Development of a subchannel model within the ANSWERS Software Service WIMS reactor physics code,” Proceedings of PHYSOR 2018, Cancun, Mexico, (April 2018). [Google Scholar]
- B. Lindley, G. Hosking, P. Smith, D. Powney, B. Tollit, T. Fry, R. Perry, T. Ware, C. Murphy, C. Grove, M. Thomas, K. Hesketh, D. Kotlyar, “Developments within the WIMS Reactor Physics Code for Whole Core Calculations,” Proceedings of International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering (2017). [Google Scholar]
- D. Basile, M. Beghi, R. Chierici, E. Salina, E. Brega, “COBRA-EN, an Upgraded Version of the COBRA-3C/MIT Code for Thermal-Hydaulic Transient Analysis of Light Water Reactor Fuel Assemblies and Cores,” Report 1010/1, ENEL-CRTN Compartimento di Milano (1999). [Google Scholar]
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