Development of a high-fidelity multi-physics coupling between MCNP6.2 and CTF4.0 for VVER applications
Creators
- 1. North Carolina State University, Burlington Laboratory, 2500 Stinson Dr, Raleigh, NC 27607 (United States)
Description
Ensuring system safety in the design, licensing, and operation phases is a priority in the nuclear industry. Performing extensive, full-scale reactor safety experiments is often prohibitive due to the large associated costs. Computational simulations offer an alternative safety analysis method, typically with significant cost reductions. Recent high-level developments in technology and increased availability of computational resources have allowed the development of high-fidelity, high-resolution multi-physics coupled codes. Such developments may be used to generate reference models for deterministic core calculations. Under this framework, the high-fidelity continuous energy Monte Carlo-based neutron transport code MCNP6.2 was coupled externally with the state-of-the-art thermal-hydraulics subchannel code, CTF4.0 for VVER (Water-Water Energetic Reactor) applications. A VVER-1000 fuel assembly model was used to demonstrate the capability of the coupled code. The converged coupled solution is compared to initial results, consisting of the first MCNP evaluation and first CTF evaluation after initialization. The VVER-1000 type assembly results are compared to other evaluations of the same assembly model. The findings indicate good agreement with expectations and reference cases, where available. The initial results of the coupled MCNP6.2/CTF4.0 calculations at the assembly level for steady-state calculations are presented in this study, which may support future work toward high-fidelity coupled full-core modeling capabilities. The multi-physics model may be further improved, enhanced, and expanded for both cycle depletion and transient applications. Such a multi-physics system will also be applicable to the VVER-1200 and other triangular lattice designs and support their deployment and operation safely and economically. (authors)
Availability note (English)
Available from the American Nuclear Society, 555 North Kensington Avenue, La Grange Park, Illinois 60526 (US)Additional details
Publishing Information
- Publisher
- ANS - American Nuclear Society
- Imprint Place
- La Grange Park (United States)
- ISBN
- 978-0-89448-787-3
- Imprint Title
- Proceedings of the international conference on physics of reactors - PHYSOR 2022
- Imprint Pagination
- 3701 p.
- Journal Page Range
- p. 1828-1837
Conference
- Title
- International conference on physics of reactors
- Acronym
- PHYSOR 2022
- Dates
- 15-20 May 2022
- Place
- Pittsburg (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 54002321
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- C CODES; COMPUTERIZED SIMULATION; CONVERGENCE; COUPLING; M CODES; NEUTRON TRANSPORT; THERMAL HYDRAULICS; WWER TYPE REACTORS
- Descriptors DEC
- COMPUTER CODES; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; MECHANICS; NEUTRAL-PARTICLE TRANSPORT; POWER REACTORS; PWR TYPE REACTORS; RADIATION TRANSPORT; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 7 refs.