Prismatic Core Coupled Transient Benchmark
Description
The Prismatic Modular Reactor (PMR) is one of the High Temperature Reactor (HTR) design concepts that have existed for some time. Several prismatic units have operated in the world (DRAGON, Fort St. Vrain, Peach Bottom) and one unit is still in operation (HTTR). The deterministic neutronics and thermal-fluids transient analysis tools and methods currently available for the design and analysis of PMRs have lagged behind the state of the art compared to LWR reactor technologies. This has motivated the development of more accurate and efficient tools for the design and safety evaluations of the PMR. In addition to the work invested in new methods, it is essential to develop appropriate benchmarks to verify and validate the new methods in computer codes. The purpose of this benchmark is to establish a well-defined problem, based on a common given set of data, to compare methods and tools in core simulation and thermal hydraulics analysis with a specific focus on transient events. The benchmark-working group is currently seeking OECD/NEA sponsorship. This benchmark is being pursued and is heavily based on the success of the PBMR-400 exercise.
Additional details
Identifiers
Publishing Information
- Imprint Pagination
- vp.
- Report number
- INL/CON--11-20811
Conference
- Title
- 2011 Annual Meeting of the American Nuclear Society (ANS)
- Dates
- 26-30 Jun 2011
- Place
- Hollywood, FL (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 43001421
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BENCHMARKS; COMPUTER CODES; DESIGN; SAFETY; SIMULATION; THERMAL HYDRAULICS; TRANSIENTS
- Descriptors DEC
- FLUID MECHANICS; HYDRAULICS; MECHANICS
Optional Information
- Contract/Grant/Project number
- AC07-05ID14517
- Funding organization
- DOE - NE (United States)