Numerical Benchmark of Strongly to Loosely Coupled Assemblies using the Transient Fission Matrix Method
Creators
- 1. DEN/CAD/DER/SPESI, CEA Cadarache, 13108 Saint Paul-Lez-Durance (France)
- 2. DEN/CAD/DER/SPRC, CEA Cadarache, 13108 Saint Paul-Lez-Durance (France)
Description
Advances in computational methods have given rise to the study and simulation of different aspects of reactor behavior. As such, topics associated with high computational costs become feasible candidates for further investigation and one of them is reactor space-time kinetics (STK). Until recently, STK simulation and point kinetics approximation were limited to deterministic codes, with Monte Carlo codes being too costly to start with. However, recent developments in this area have allowed the use of certain methods in stochastic codes. One such technique is based on the Transient Fission Matrix (TFM) model, a hybrid method that uses a system response obtained through Monte Carlo and stored in fission and time matrices as input for deterministic calculations. The result enables a view of the STK in terms of neutron propagation probability and propagation time across the system. The TFM method was applied to a simple coupled core configuration to generate a numerical benchmark. The Serpent 2 Monte Carlo code was used for the stochastic part of the calculation. The configuration consists of two fuel assemblies placed in a light water tank, with a water blade of varying width between them. TFM, flux and fission results were obtained for varying water blade widths, ranging between 0 cm and 20 cm. The data is then used to analyze the behavior of the system, as well as the effects of the coupling between the two assemblies. As the assemblies move further apart, the system slowly transitions from two tightly coupled assemblies that essentially form a single core, to two almost independent cores. This study enables to produce a benchmark for future calculations and predefine an innovative way of designing high dominant ratio configurations, required for tackling Monte Carlo residual problems. An actual experimental program could be led in ad hoc zero power reactor (ZPR), such as the KUCA reactor of Kyoto University.
Availability note (English)
Available from https://www.epj-conferences.org/articles/epjconf/pdf/2021/01/epjconf_physor2020_06038.pdf; https://doaj.org/article/a2ec53995390464fa07e126855f22d39Additional details
Identifiers
Publishing Information
- Journal Title
- EPJ. Web of Conferences
- Journal Volume
- 247
- Journal Page Range
- vp.
- ISSN
- 2100-014X
Conference
- Title
- International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future
- Acronym
- PHYSOR2020
- Dates
- 28 Mar - 2 Apr 2020
- Place
- Cambridge (United Kingdom)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 53088031
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCHMARKS; COMPUTERIZED SIMULATION; CONFIGURATION; COUPLING; DESIGN; FISSION; FUEL ASSEMBLIES; KINETICS; KUCA REACTOR; MATRICES; MONTE CARLO METHOD; NEUTRONS; SPACE-TIME; STOCHASTIC PROCESSES; TRANSIENTS
- Descriptors DEC
- BARYONS; CALCULATION METHODS; ELEMENTARY PARTICLES; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FERMIONS; GRAPHITE MODERATED REACTORS; HADRONS; NUCLEAR REACTIONS; NUCLEONS; REACTORS; RESEARCH AND TEST REACTORS; SIMULATION; WATER MODERATED REACTORS; ZERO POWER REACTORS