Simulations of single- and two-phase shock tubes and gravity-driven wave problems with the RELAP-7 nuclear reactor system analysis code

Delchini, Marc O.; Ragusa, Jean C.; Berry, Ray A.

doi:10.1016/j.nucengdes.2017.04.034

Title: Simulations of single- and two-phase shock tubes and gravity-driven wave problems with the RELAP-7 nuclear reactor system analysis code

Full Record
Other Related Research

Abstract

Propagation of pressure waves in single and two-phase flows is of key interest for nuclear safety analyses, reactor design, construction and life extension of nuclear reactors. In this work, we assess the capabilities of RELAP-7, the next-generation nuclear reactor system code, to solve single- and two-phase flows developing pressure waves. RELAP-7 is based on a 7-equation, two-phase flow model, with distinct phasic pressures. It is well established that these hyperbolic conservation laws can develop shocks and discontinuities and thus, require a stabilization numerical method. The all-Mach flow Entropy Viscosity Method (EVM) is now employed in RELAP-7 as a viscous stabilization approach. In this paper, we briefly describe the implementation of the EVM and use open-literature test cases that exhibit pressure waves to show that the entropy viscosity method performs adequately for these single- and two-phase cases.

Authors:

Delchini, Marc O. ^[1]; Ragusa, Jean C. ^[2]; Berry, Ray A. ^[3]

Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Texas A & M Univ., College Station, TX (United States)
Idaho National Lab. (INL), Idaho Falls, ID (United States)

Publication Date:: Fri May 12 00:00:00 EDT 2017

Research Org.:: Idaho National Lab. (INL), Idaho Falls, ID (United States); Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

Sponsoring Org.:: USDOE Office of Nuclear Energy (NE)

OSTI Identifier:: 1396017

Alternate Identifier(s):: OSTI ID: 1394240; OSTI ID: 1682379

Report Number(s):: INL/JOU-16-39762
Journal ID: ISSN 0029-5493; PII: S0029549317302145

Grant/Contract Number:: AC07-05ID14517; AC05-00OR22725

Resource Type:: Accepted Manuscript

Journal Name:: Nuclear Engineering and Design

Additional Journal Information:: Journal Volume: 319; Journal Issue: C; Journal ID: ISSN 0029-5493

Publisher:: Elsevier

Country of Publication:: United States

Language:: English

Subject:: 97 MATHEMATICS AND COMPUTING; 22 GENERAL STUDIES OF NUCLEAR REACTORS; 42 ENGINEERING; entropy viscosity method; low-Mach flow; pressure waves; RELAP-7; seven-equation model; single phase flows; two-phase flows; waterhammer

Citation Formats


                    Delchini, Marc O., Ragusa, Jean C., and Berry, Ray A. Simulations of single- and two-phase shock tubes and gravity-driven wave problems with the RELAP-7 nuclear reactor system analysis code.  United States: N. p., 2017. 
Web.  doi:10.1016/j.nucengdes.2017.04.034.

Copy to clipboard


                    Delchini, Marc O., Ragusa, Jean C., & Berry, Ray A. Simulations of single- and two-phase shock tubes and gravity-driven wave problems with the RELAP-7 nuclear reactor system analysis code.  United States.  https://doi.org/10.1016/j.nucengdes.2017.04.034

Copy to clipboard


                    Delchini, Marc O., Ragusa, Jean C., and Berry, Ray A. Fri .  
"Simulations of single- and two-phase shock tubes and gravity-driven wave problems with the RELAP-7 nuclear reactor system analysis code".  United States.  https://doi.org/10.1016/j.nucengdes.2017.04.034.  https://www.osti.gov/servlets/purl/1396017.

Copy to clipboard


                    
@article{osti_1396017,

  title        = {Simulations of single- and two-phase shock tubes and gravity-driven wave problems with the RELAP-7 nuclear reactor system analysis code},

  author       = {Delchini, Marc O. and Ragusa, Jean C. and Berry, Ray A.},

  abstractNote = {Propagation of pressure waves in single and two-phase flows is of key interest for nuclear safety analyses, reactor design, construction and life extension of nuclear reactors. In this work, we assess the capabilities of RELAP-7, the next-generation nuclear reactor system code, to solve single- and two-phase flows developing pressure waves. RELAP-7 is based on a 7-equation, two-phase flow model, with distinct phasic pressures. It is well established that these hyperbolic conservation laws can develop shocks and discontinuities and thus, require a stabilization numerical method. The all-Mach flow Entropy Viscosity Method (EVM) is now employed in RELAP-7 as a viscous stabilization approach. In this paper, we briefly describe the implementation of the EVM and use open-literature test cases that exhibit pressure waves to show that the entropy viscosity method performs adequately for these single- and two-phase cases.},

  doi          = {10.1016/j.nucengdes.2017.04.034},

  journal      = {Nuclear Engineering and Design},

  number       = C,

  volume       = 319,

  place        = {United States},

  year         = {Fri May 12 00:00:00 EDT 2017},

  month        = {Fri May 12 00:00:00 EDT 2017}

}

Copy to clipboard

Journal Article:

Free Publicly Available Full Text

Accepted Manuscript (Publisher)

Accepted Manuscript (DOE)

Publisher's Version of Record

https://doi.org/10.1016/j.nucengdes.2017.04.034

Other availability

Search WorldCat to find libraries that may hold this journal

Citation Metrics:

Cited by: 4 works

Citation information provided by
Web of Science

Save / Share:

Export Metadata

Save to My Library

Similar Records in DOE PAGES and OSTI.GOV collections:

RELAP-7 Numerical Stabilization: Entropy Viscosity Method

Technical Report Berry, R. A. ; Delchini, M. O. ; Ragusa, J.

The RELAP-7 code is the next generation nuclear reactor system safety analysis code being developed at the Idaho National Laboratory (INL). The code is based on the INL's modern scientific software development framework, MOOSE (Multi-Physics Object Oriented Simulation Environment). The overall design goal of RELAP-7 is to take advantage of the previous thirty years of advancements in computer architecture, software design, numerical integration methods, and physical models. The end result will be a reactor systems analysis capability that retains and improves upon RELAP5's capability and extends the analysis capability for all reactor system simulation scenarios. RELAP-7 utilizes a single phasemore »« less
https://doi.org/10.2172/1149027

Full Text Available
Preliminary Study on the Suitability of a Second-Order Reconstructed Discontinuous Galerkin Method for RELAP-7 Thermal-Hydraulic Modeling

Technical Report Xia, Yidong ; Hansel, Joshua ; Berry, Ray A. ; ...

This document presents a preliminary study on the suitability of a second-order reconstructed discontinuous Galerkin (rDG) method for RELAP-7 thermal-hydraulic modeling. The document begins with a brief description of the governing equations for compressible, two-phase vapor and liquid flow, with a presentation of the seven-equation formulation details. A comparative study between the second-order rDG method and the RELAP-7's finite element method (FEM) with a entropy viscosity method (EVM) based numerical stabilization scheme (namely FEM-EVM) over a series of benchmark test problems is demonstrated. The intent for this suite of test problems is to provide baseline comparison data that demonstrate themore »« less
https://doi.org/10.2172/1468483

Full Text Available
RELAP-7 Beta Release: Summary of Capabilities

Technical Report Martineau, Richard C. ; Zhang, Hongbin ; Zhao, Haihua

RELAP-7 is a nuclear systems safety analysis code being developed at the Idaho National Laboratory (INL). Building upon the decades of software development at the INL, we began the development of RELAP-7 in 2011 to support the Risk Informed Safety Margins Characterization (RISMC) Pathway. As part of this development, the first lines of RELAP-7 code were committed to the software revision control repository on November 7th, 2011. The overall design goal of RELAP-7 is to take advantage of the previous thirty years of advancements in computer architecture, software design, numerical methods, and physical models in order to provide capabilities neededmore »« less
https://doi.org/10.2172/1177638

Full Text Available
RELAP-7 Progress Report. FY-2015 Optimization Activities Summary

Technical Report Berry, Ray Alden ; Zou, Ling ; Andrs, David

This report summarily documents the optimization activities on RELAP-7 for FY-2015. It includes the migration from the analytical stiffened gas equation of state for both the vapor and liquid phases to accurate and efficient property evaluations for both equilibrium and metastable (nonequilibrium) states using the Spline-Based Table Look-up (SBTL) method with the IAPWS-95 properties for steam and water. It also includes the initiation of realistic closure models based, where appropriate, on the U.S. Nuclear Regulatory Commission’s TRACE code. It also describes an improved entropy viscosity numerical stabilization method for the nonequilibrium two-phase flow model of RELAP-7. For ease of presentationmore »« less
https://doi.org/10.2172/1244637

Full Text Available
Developing A Fully Implicit Compressible Flow Valve Model in RELAP-7 and Its Application in Short Term BWR Station Black-Out Analyses

Conference Zhao, Haihua ; Zou, Ling ; Zhang, Hongbin

This paper presents a set of dynamical models for SRV simulation and their implementation in the RELAP-7 code, which is a new reactor system analysis code being developed at INL. RELAP-7 is based on the MOOSE (the Multi-Physics Object-Oriented Simulation Environment) framework. The compressible flow SRV model covers three different sets of models: fully closed case, subsonic case, and choking case. The RELAP-7 is a fully implicit code and the preconditioned Jacobian-free Newton-Krylov (JFNK) method is used to solve the discretized nonlinear problem. The JFNK method generally needs a good preconditioning scheme to be effective and efficient. There are differentmore »« less
Full Text Available

Similar Records