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

Title: Evaluation of CFD Methods for Simulation of Two-Phase Boiling Flow Phenomena in a Helical Coil Steam Generator

Abstract

The U.S. Department of Energy, Office of Nuclear Energy charges participants in the Nuclear Energy Advanced Modeling and Simulation (NEAMS) program with the development of advanced modeling and simulation capabilities that can be used to address design, performance and safety challenges in the development and deployment of advanced reactor technology. The NEAMS has established a high impact problem (HIP) team to demonstrate the applicability of these tools to identification and mitigation of sources of steam generator flow induced vibration (SGFIV). The SGFIV HIP team is working to evaluate vibration sources in an advanced helical coil steam generator using computational fluid dynamics (CFD) simulations of the turbulent primary coolant flow over the outside of the tubes and CFD simulations of the turbulent multiphase boiling secondary coolant flow inside the tubes integrated with high resolution finite element method assessments of the tubes and their associated structural supports. This report summarizes the demonstration of a methodology for the multiphase boiling flow analysis inside the helical coil steam generator tube. A helical coil steam generator configuration has been defined based on the experiments completed by Polytecnico di Milano in the SIET helical coil steam generator tube facility. Simulations of the defined problem have beenmore » completed using the Eulerian-Eulerian multi-fluid modeling capabilities of the commercial CFD code STAR-CCM+. Simulations suggest that the two phases will quickly stratify in the slightly inclined pipe of the helical coil steam generator. These results have been successfully benchmarked against both empirical correlations for pressure drop and simulations using an alternate CFD methodology, the dispersed phase mixture modeling capabilities of the open source CFD code Nek5000.« less

Authors:
 [1];  [2];  [1];  [2];  [2]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  2. Argonne National Lab. (ANL), Argonne, IL (United States)
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1335356
Report Number(s):
ORNL/TM-2016/612
NT0512000; NENT026; TRN: US1700827
DOE Contract Number:
AC05-00OR22725
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 97 MATHEMATICS AND COMPUTING; COMPUTERIZED SIMULATION; STEAM GENERATORS; FINITE ELEMENT METHOD; BOILING; PRIMARY COOLANT CIRCUITS; TUBES; FLUID MECHANICS; EVALUATION; SUPPORTS; PRESSURE DROP; MECHANICAL VIBRATIONS; BENCHMARKS; CORRELATIONS; DESIGN; MITIGATION; PERFORMANCE; HELICAL CONFIGURATION; TURBULENT FLOW; TWO-PHASE FLOW

Citation Formats

Pointer, William David, Shaver, Dillon, Liu, Yang, Vegendla, Prasad, and Tentner, Adrian. Evaluation of CFD Methods for Simulation of Two-Phase Boiling Flow Phenomena in a Helical Coil Steam Generator. United States: N. p., 2016. Web. doi:10.2172/1335356.
Pointer, William David, Shaver, Dillon, Liu, Yang, Vegendla, Prasad, & Tentner, Adrian. Evaluation of CFD Methods for Simulation of Two-Phase Boiling Flow Phenomena in a Helical Coil Steam Generator. United States. doi:10.2172/1335356.
Pointer, William David, Shaver, Dillon, Liu, Yang, Vegendla, Prasad, and Tentner, Adrian. Fri . "Evaluation of CFD Methods for Simulation of Two-Phase Boiling Flow Phenomena in a Helical Coil Steam Generator". United States. doi:10.2172/1335356. https://www.osti.gov/servlets/purl/1335356.
@article{osti_1335356,
title = {Evaluation of CFD Methods for Simulation of Two-Phase Boiling Flow Phenomena in a Helical Coil Steam Generator},
author = {Pointer, William David and Shaver, Dillon and Liu, Yang and Vegendla, Prasad and Tentner, Adrian},
abstractNote = {The U.S. Department of Energy, Office of Nuclear Energy charges participants in the Nuclear Energy Advanced Modeling and Simulation (NEAMS) program with the development of advanced modeling and simulation capabilities that can be used to address design, performance and safety challenges in the development and deployment of advanced reactor technology. The NEAMS has established a high impact problem (HIP) team to demonstrate the applicability of these tools to identification and mitigation of sources of steam generator flow induced vibration (SGFIV). The SGFIV HIP team is working to evaluate vibration sources in an advanced helical coil steam generator using computational fluid dynamics (CFD) simulations of the turbulent primary coolant flow over the outside of the tubes and CFD simulations of the turbulent multiphase boiling secondary coolant flow inside the tubes integrated with high resolution finite element method assessments of the tubes and their associated structural supports. This report summarizes the demonstration of a methodology for the multiphase boiling flow analysis inside the helical coil steam generator tube. A helical coil steam generator configuration has been defined based on the experiments completed by Polytecnico di Milano in the SIET helical coil steam generator tube facility. Simulations of the defined problem have been completed using the Eulerian-Eulerian multi-fluid modeling capabilities of the commercial CFD code STAR-CCM+. Simulations suggest that the two phases will quickly stratify in the slightly inclined pipe of the helical coil steam generator. These results have been successfully benchmarked against both empirical correlations for pressure drop and simulations using an alternate CFD methodology, the dispersed phase mixture modeling capabilities of the open source CFD code Nek5000.},
doi = {10.2172/1335356},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Sep 30 00:00:00 EDT 2016},
month = {Fri Sep 30 00:00:00 EDT 2016}
}

Technical Report:

Save / Share:
  • A test transient performed at a helical coil sodium-to-water steam generator test facility was simulated using the MINET code. It was determined that correct calculation of the sodium outlet temperature requires representation of heat capacitance of the structure.
  • Equations and constitutive relations describing two-dimensional, thermally expandable, homogeneous, two-phase flow are presented and discussed. Four numerical solution methods of these equations are reviewed in detail. A fully and linearly implicit numerical method is developed that utilizes a dual variable transformation technique to substantially reduce the size of the matrix required for inversion at each time step. A computer code (DUVAL) incorporating this dual variable method is discussed, and preliminary numerical results are presented.
  • The two helical coils representing the steam generator in the CNSG-IV were tested in the Steam Generator Test Facility of the Alliance Research Center (ARC). This facility combines the capabilities of the Hot Water Test Facility and the Once-Through Steam Generator (OTSG) Test Facility to test steam generators at full system pressures and temperatures for both the primary and secondary sides using water as the test fluid. The report provides the arrangement schematic of the Steam Generator Test Facility used during the functional performance tests of the helical coil steam generator (HCSG). It emphasizes only that equipment used during themore » helical coil test. An OTSG ('A' generator) was also used to provide an additional heat sink so the primary side furnace could be fired at a higher rate, yet be within its controllable range. (GRA)« less
  • The objective of this project was to study the functional performance of the CNSG - IV helical steam generator to demonstrate that the generator meets steady-state and transient thermal-hydraulic performance specifications and that secondary flow instability will not be a problem. Economic success of the CNSG concepts depends to a great extent on minimizing the size of the steam generator and the reactor vessel for ship installation. Also, for marine application the system must meet stringent specifications for operating stability, transient response, and control. The full-size two-tube experimental unit differed from the CNSG only in the number of tubes andmore » the mode of primary flow. In general, the functional performance test demonstrated that the helical steam generator concept will exceed the specified superheat of 35F at 100% load. The experimental measured superheat at comparable operating conditions was 95F. Testing also revealed that available computer codes accurately predict trends and overall performance characteristics. (GRA)« less