Coupling of Pronghorn and RELAP-7 for a Pebble Bed Reactor
Conference
·
OSTI ID:1668350
- Idaho National Laboratory
- University of California, Berkeley
High temperature gas cooled reactors (HTGR) are a candidate for timely Gen-IV reactor technology deployment because of high technology readiness and walk-away safety. Among HTGRs, pebble bed reactors (PBRs) have attractive features such as low excess reactivity and online refueling. Pebble bed reactors pose unique challenges to analysts and reactor designers such as continuous burnup distribution depending on pebble motion and recirculation, radiative heat transfer across a variety of gas-filled gaps, and long design basis transients such as pressurized and depressurized loss of forced circulation. Modeling and simulation is essential for both the PBR’s safety case and design process. In order to verify and validate the new generation codes the Nuclear Energy Agency (NEA) Data bank provide a set of benchmarks data together with solutions calculated by the participants using the state of the art codes of that time. An important milestone to test the new PBR simulation codes is the OECD NEA PBMR-400 benchmark which includes thermal hydraulic and neutron kinetic standalone exercises as well as coupled exercises and transients scenarios. In this work, the reactor multiphysics code MAMMOTH and the thermal hydraulics code Pronghorn, both developed by the Idaho National Laboratory (INL) within the multiphysics object-oriented simulation environment (MOOSE), have been used to solve Phase 1 exercises 1 and 2 of the PBMR-400 benchmark. The steady state results are in agreement with the other participants’ solutions demonstrating the adequacy of MAMMOTH and Pronghorn for simulating PBRs.
- Research Organization:
- Idaho National Laboratory (INL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy (NE)
- DOE Contract Number:
- AC07-05ID14517
- OSTI ID:
- 1668350
- Report Number(s):
- INL/CON-19-54415-Rev000
- Country of Publication:
- United States
- Language:
- English
Similar Records
Deployment of the Finite Volume Method in Pronghorn for Gas and Salt cooled Pebble Bed Reactors
The OECD/NEA/NSC PBMR coupled neutronics/thermal hydraulics transient benchmark: The PBMR-400 core design
Pronghorn: A Multidimensional Coarse Mesh Application for Advanced Reactor Thermal-Hydraulics
Technical Report
·
Tue Jun 01 00:00:00 EDT 2021
·
OSTI ID:2008349
The OECD/NEA/NSC PBMR coupled neutronics/thermal hydraulics transient benchmark: The PBMR-400 core design
Conference
·
Sat Jul 01 00:00:00 EDT 2006
·
OSTI ID:22039681
Pronghorn: A Multidimensional Coarse Mesh Application for Advanced Reactor Thermal-Hydraulics
Journal Article
·
Thu Feb 11 23:00:00 EST 2021
· Nuclear Technology
·
OSTI ID:2006641