skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Coupled Multiphysics Simulations of Heat Pipe Microreactors Using DireWolf

Journal Article · · Nuclear Technology

DireWolf is a multiphysics software driver application designed to simulate heat pipe–cooled nuclear microreactors. Developed under the U.S. Department of Energy, Office of Nuclear Energy Nuclear Energy Advanced Modeling and Simulation (NEAMS) program, the DireWolf software application’s objective is to provide the nuclear community with a design and safety analysis simulation capability. Based upon the NEAMS program Multiphysics Object-Oriented Simulation Environment (MOOSE) computational framework, DireWolf tightly couples nuclear microreactor physics, reactor physics, radiation transport, nuclear fuel performance, heat pipe thermal hydraulics, power generation, and structural mechanics to resolve the interdependent nonlinearities. DireWolf is capable of simulating both steady and transient normal reactor operation and several postulated failure scenarios. We will present the fundamental physics of heat pipe–cooled nuclear microreactors and the MOOSE-based software employed in DireWolf. Both steady and transient results for coupled reactor physics, radiation transport, and nuclear fuel performance are demonstrated.

Research Organization:
Los Alamos National Laboratory (LANL), Los Alamos, NM (United States); Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE)
Grant/Contract Number:
89233218CNA000001; AC07-05ID14517
OSTI ID:
1812664
Report Number(s):
LA-UR-20-27268; TRN: US2213269
Journal Information:
Nuclear Technology, Vol. 207, Issue 7; ISSN 0029-5450
Publisher:
Taylor & Francis - formerly American Nuclear Society (ANS)Copyright Statement
Country of Publication:
United States
Language:
English

References (29)

Multidimensional multiphysics simulation of nuclear fuel behavior journal April 2012
Sodium heat pipe module test for the SAFE-30 reactor prototype conference January 2001
Continuous Integration, In-Code Documentation, and Automation for Nuclear Quality Assurance Conformance journal January 2021
Hybrid P N - S N with Lagrange multiplier and upwinding for the multiscale transport capability in Rattlesnake journal November 2017
Rattlesnake: A MOOSE-Based Multiphysics Multischeme Radiation Transport Application journal April 2021
PROTEUS-MOC User Manual report September 2018
MOOSE: Enabling massively parallel multiphysics simulation journal January 2020
MC 2 -3: Multigroup Cross Section Generation Code for Fast Reactor Analysis journal June 2017
3D modeling of missing pellet surface defects in BWR fuel journal October 2016
SAFE-100 Module Fabrication and Test
  • Ring, Peter J.
  • SPACE TECHNOLOGY AND APPLICATIONS INT.FORUM-STAIF 2003: Conf.on Thermophysics in Microgravity; Commercial/Civil Next Generation Space Transportation; Human Space Exploration; Symps.on Space Nuclear Power and Propulsion (20th); Space Colonization (1st), AIP Conference Proceedings https://doi.org/10.1063/1.1541282
conference January 2003
Permeability and effective pore radius measurements for heat pipe and fuel cell applications journal March 2006
hypre: A Library of High Performance Preconditioners
  • Falgout, Robert D.; Yang, Ulrike Meier; Goos, Gerhard
  • Computational Science — ICCS 2002: International Conference Amsterdam, The Netherlands, April 21–24, 2002 Proceedings, Part III https://doi.org/10.1007/3-540-47789-6_66
book April 2002
Hybrid super homogenization and discontinuity factor method for continuous finite element diffusion journal June 2019
A Newton solution for the Superhomogenization method: The PJFNK-SPH journal January 2018
libMesh : a C++ library for parallel adaptive mesh refinement/coarsening simulations journal November 2006
KRUSTY Reactor Design journal June 2020
A two-phase mixture theory for the deflagration-to-detonation transition (ddt) in reactive granular materials journal November 1986
Physics-based multiscale coupling for full core nuclear reactor simulation journal October 2015
SNAP 10A, First Reactor in Space
  • Johnson, Richard A.; Morgan, William T.; Rocklin, Sol R.
  • Aeronautic and Space Engineering and Manufacturing Meeting, SAE Technical Paper Series https://doi.org/10.4271/650793
conference October 1965
Multiscale development of a fission gas thermal conductivity model: Coupling atomic, meso and continuum level simulations journal September 2013
The discrete equation method (DEM) for fully compressible, two-phase flows in ducts of spatially varying cross-section journal November 2010
Kilopower Project: The KRUSTY Fission Power Experiment and Potential Missions journal June 2020
Review of liquid metal heat pipe work at Los Alamos
  • Reid, Robert S.; Merrigan, Michael A.; Sena, J. Tom
  • Proceedings of the eighth symposium on space nuclear power systems, AIP Conference Proceedings https://doi.org/10.1063/1.40058
conference January 1991
Special Purpose Nuclear Reactor (5 MW) for Reliable Power at Remote Sites Assessment Report report April 2017
The Serpent Monte Carlo code: Status, development and applications in 2013 journal August 2015
Results of the KRUSTY Nuclear System Test journal June 2020
Transient Two-Dimensional Compressible Analysis for High-Temperature heat Pipes with Pulsed heat Input journal January 1991
Mechanistic materials modeling for nuclear fuel performance journal July 2017
Verification of the BISON fuel performance code journal September 2014