On the novel 3-D neutron transport kinetic tRAPID algorithm and its validation
Creators
- 1. Virginia Tech, Nuclear Engineering Program, 7054 Haycock Road, Falls Church, VA 22043 (United States)
- 2. Jozef Stefan Institute, Reactor Physics Department, Jamova Cesta 39, Si-1000 Ljubljana (Slovenia)
Description
The Real-time Analysis for Particle-transport and In-situ Detection (RAPID) Code System, based on the Multi-stage Response-function Transport (MRT) methodology, allows for real-time simulation of nuclear systems based on 3-D continuous-energy particle transport. RAPID's steady-state (criticality) neutron transport algorithm is based on the Fission Matrix (FM) method, and has been extensively verified and validated against computational benchmarks and experiments. This paper introduces the novel 3-D time-dependent transport algorithm that has been implemented into the code, tRAPID, and its validation using the JSI TRIGA Mark-II reactor. tRAPID accurately and efficiently calculates neutron kinetics parameters (such as βeff, leff , Λ, αRossi) and 3-D time-dependent neutron fission source distribution and neutron importances for both prompt and delayed neutrons. tRAPID is used to simulate a rod insertion experiment performed at the JSI TRIGA Mark-II reactor, during which signals from four fission chambers at four different locations in the core were collected. The results demonstrate how tRAPID is capable of calculating detailed and accurate results with only a minimal use computational resources and time
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. 2269-2279
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
- 54002366
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCHMARKS; COMPUTERIZED SIMULATION; NEUTRON TRANSPORT THEORY; R CODES; REACTIVITY INSERTIONS; REACTOR KINETICS; REACTOR KINETICS EQUATIONS; RESPONSE FUNCTIONS; TRANSFER MATRIX METHOD; VALIDATION
- Descriptors DEC
- CALCULATION METHODS; COMPUTER CODES; EQUATIONS; FUNCTIONS; KINETICS; SIMULATION; TESTING; TRANSPORT THEORY
Optional Information
- Notes
- 15 refs.