Coupling of CTF and RELAP5-3D Within an Enhanced Fidelity Nuclear Power Plant Simulator

被引:1
|
作者
Wysocki, Aaron J. J. [1 ]
Salko, Robert K. K. [1 ]
Arshavsky, Igor [2 ]
机构
[1] Oak Ridge Natl Lab, Nucl Energy & Fuel Cycle Div, Oak Ridge, TN 37830 USA
[2] WSC Inc, Frederick, MD USA
关键词
Nuclear plant simulator; multiphysics; thermal hydraulics; light water reactor; transient analysis; METHODOLOGY;
D O I
10.1080/00295450.2023.2175596
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
A robust and accurate multiphysics engineering simulator is being developed to model the core behavior and system response of pressurized water reactors. This simulator relies on the NESTLE and CTF computer codes to model the neutronics and thermal hydraulics (TH), respectively, inside the core on a nodal scale and on the Reactor Excursion and Leak Analysis Program-Three Dimensional (RELAP5-3D) to model the entire nuclear steam supply system. The RELAP5-3D model includes highly detailed nodalization and multidimensional flow modeling throughout the vessel. Previously, pin-resolved data generated via the Virtual Environment for Reactor Analysis core simulator were used to improve the accuracy of the NESTLE core predictions. The engineering simulator being developed as part of this work uses the 3KEYMASTER platform to couple the enhanced NESTLE model to a nodal-fidelity CTF model to balance run time with accuracy; NESTLE provides node-dependent powers to CTF, and CTF provides node-dependent coolant densities and fuel temperatures to NESTLE.An overlapping domain approach is used for the core TH in which RELAP5-3D provides core boundary conditions based on the system response and CTF provides a node-dependent coolant heating rate to the RELAP5-3D core solution. In the preliminary TH demonstration discussed in this paper, CTF and RELAP5-3D provided similar steady-state core predictions, indicating the hydraulic compatibility between the codes, as well as reasonable and expected behavior under hypothetical transient conditions. This provides an initial step in ongoing efforts toward a robust, multiscale TH/neutronics engineering simulator capability.
引用
收藏
页码:1466 / 1484
页数:19
相关论文
共 50 条
  • [21] RelapManager: A Safety Analysis Automation Framework and Software for RELAP5-3D
    Martin, Robert P.
    Morgan, Simone H.
    Cragg, Christopher
    NUCLEAR TECHNOLOGY, 2016, 193 (01) : 200 - 212
  • [22] ANALYSIS OF LEAKS THROUGH MICROCHANNEL CRACKS USING RELAP5-3D
    Frisani, Angelo
    Hassan, Yassin A.
    NUCLEAR TECHNOLOGY, 2009, 167 (02) : 304 - 312
  • [23] Validation of RELAP5-3D RBMK-1500 reactor model
    Uspuras, E
    Kaliatka, A
    Bubelis, E
    NUCLEAR ENERGY-JOURNAL OF THE BRITISH NUCLEAR ENERGY SOCIETY, 2004, 43 (05): : 257 - 264
  • [24] Experimental study of a natural circulation loop and RELAP5-3D analysis
    Bertani, C.
    Falcone, N.
    Bersano, A.
    Azzarone, A.
    De Salve, M.
    Panella, B.
    37TH UIT HEAT TRANSFER CONFERENCE, 2020, 1599
  • [25] VVER-1000 model assessment using RELAP5-3D
    Popov, EL
    Yoder, GL
    Velichkov, V
    NUCLEAR TECHNOLOGY, 2005, 149 (03) : 304 - 308
  • [26] Coupling of RELAP and LabVIEW to Model a Nuclear Power Plant System Realistically
    Pack, J. C.
    Fu, Z.
    Aydogan, F.
    ASME INTERNATIONAL MECHANICAL ENGINEERING CONGRESS AND EXPOSITION, 2014, VOL 6B, 2015,
  • [27] A coupled RELAP5-3D/CFD methodology with a proof-of-principle calculation
    Aumiller, DL
    Tomlinson, ET
    Bauer, RC
    NUCLEAR ENGINEERING AND DESIGN, 2001, 205 (1-2) : 83 - 90
  • [28] SENSITIVITY STUDY OF THE SOUTH TEXAS PROJECT POWER PLANT STEADY-STATE SIMULATIONS USING RELAP5-3D COUPLED WITH DAKOTA
    Rodriguez, O. A.
    Vaghetto, R.
    Hassan, Y. A.
    PROCEEDINGS OF THE 20TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING AND THE ASME 2012 POWER CONFERENCE - 2012, VOL 5, 2012, : 595 - 602
  • [29] Comparison of MYRRHA RELAP5 MOD 3.3 and RELAP5-3D Models on Steady State and PLOF Transient
    Castelliti, D.
    Hamidouche, T.
    NUCLEAR TECHNOLOGY, 2016, 193 (01) : 36 - 46
  • [30] Use of RELAP5-3D for dynamic analysis of a closed-loop Brayton cycle coupled to a nuclear reactor
    McCann, Larry D.
    Space Technology and Applications International Forum - STAIF 2007, 2007, 880 : 541 - 550