A Well-Posed Two Phase Flow Model and its Numerical Solutions for Reactor Thermal-Fluids Analysis
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
A 7-equation two-phase flow model and its numerical implementation is presented for reactor thermal-fluids applications. The equation system is well-posed and treats both phases as compressible flows. The numerical discretization of the equation system is based on the finite element formalism. The numerical algorithm is implemented in the next generation RELAP-7 code (Idaho National Laboratory (INL)’s thermal-fluids code) built on top of an other INL’s product, the massively parallel multi-implicit multi-physics object oriented code environment (MOOSE). Some preliminary thermal-fluids computations are presented.
- Research Organization:
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy (NE)
- DOE Contract Number:
- AC-07-05-ID14517
- OSTI ID:
- 1313939
- Report Number(s):
- INL/EXT-16-39603; TRN: US1601829
- Country of Publication:
- United States
- Language:
- English
Similar Records
RELAP-7 Level 2 Milestone Report: Demonstration of a Steady State Single Phase PWR Simulation with RELAP-7
RELAP-7 Closure Correlations
RELAP-7 Beta Release: Summary of Capabilities
Technical Report
·
Tue May 01 00:00:00 EDT 2012
·
OSTI ID:1313939
+5 more
RELAP-7 Closure Correlations
Technical Report
·
Sat Apr 01 00:00:00 EDT 2017
·
OSTI ID:1313939
+5 more
RELAP-7 Beta Release: Summary of Capabilities
Technical Report
·
Mon Dec 01 00:00:00 EST 2014
·
OSTI ID:1313939