CFD/RELAP5 Coupling Analysis of the ISP No. 43 Boron Dilution Experiment

다국어 초록 (Multilingual Abstract)

Multi-dimensional coupling analysis is a research hot spot in nuclear reactor thermal hydraulic study and both the full-scale system transient response and local key three-dimensional thermal hydraulic phenomenon could be obtained simultaneously, which can achieve the balance between efficiency and accuracy in the numerical simulation of nuclear reactor. A one-dimensional to three-dimensional (1D-3D) coupling platform for the nuclear reactor multi-dimensional analysis is developed by XJTU-NuTheL (Nuclear Thermal-hydraulic Laboratory at Xi'an Jiaotong University) based on the CFD code Fluent and system code RELAP5 through the Dynamic Link Library (DLL) technology and Fluent user-defined functions (UDF). In this paper, the International Standard Problem (ISP) No. 43 is selected as the benchmark and the rapid boron dilution transient in the nuclear reactor is studied with the coupling code. The code validation is conducted first and the numerical simulation results show good agreement with the experimental data. The three-dimensional flow and temperature fields in the downcomer are analyzed in detail during the transient scenarios. The strong reverse flow is observed beneath the inlet cold leg, causing the de-borated water slug to mainly diffuse in the circumferential direction. The deviations between the experimental data and the transients predicted by the coupling code are also discussed.

참고문헌 (Reference)

1 B. J. Daly, "Three-dimensional Calculations of Transient Fluid-Thermal Mixing in the Downcomer of the Calvert Cliffs-1 Plant Using SOLA-PTS" Los Alamos National Lab 1984

2 A. Petruzzi, "Thermal-hydraulic system codes in nulcear reactor safety and qualification procedures" 460795-, 2008

3 D. Bestion, "System Code Models and Capabilities, Thicket-2008"

4 H. Yu, "Study of boron diffusion models and dilution accidents in nuclear reactor : a comprehensive review" 148 : 107659-, 2020

5 M. Wang, "Recent progress of CFD applications in PWR thermal hydraulics study and future directions" 150 : 107836-, 2021

6 V. H. Ransom, "RELAP5/MOD3. 3 Code Manual Volume IV:Models and Correlations NUREG/CR-5535/Rev 1" Idaho National Engineering Laboratory 2001

7 W. Li, "Preliminary study of coupling CFD code FLUENT and system code RELAP5" 73 : 96-107, 2014

8 D. Pialla, "Overview of the system alone and system/CFD coupled calculations of the PHENIX Natural Circulation Test within the THINS project" 290 : 78-86, 2015

9 T. Feng, "Numerical research on water hammer phenomenon of parallel pump-valve system by coupling FLUENT with RELAP5" 109 : 318-326, 2017

10 M. Gavrilas, "International standard problem (ISP) No. 43 rapid boron dilution transient tests for code verification" NEA/CSNI 2001

11 A. Tanrikut, "In-tube steam condensation in the presence of air under transient conditions" Office of Nuclear Regulatory Research, US Nuclear Regulatory Commission 2007

12 A. Papukchiev, "Extension of the Simulation Capabilities of the 1D System Code ATHLET by Coupling with the 3D CFD Software Package ANSYS CFX"

13 H. Yu, "Development and validation of boron diffusion model in nuclear reactor core subchannel analysis" 130 : 208-217, 2019

14 H. Prasser, "Coolant Mixing in a PWR-Deboration Transients, Steam Line Breaks and Emergency Core Cooling Injection-Experiments and Analyses, vol. 143"

15 T. Grunloh, "Comparison of overlapping and separate domain coupling methods"

16 A. Papukchiev, "Comparison of different coupling CFDeSTH approaches for pre-test analysis of a TALL-3D experiment" 290 : 135-143, 2015

17 J. Li, "CFD simulation on the transient process of coolant mixing phenomenon in reactor pressure vessel" 153 : 2021

18 R.C. Jones, "Boron Dilution Reactivity Transients A Regulatory Perspective" Nuclear Energy Agency of the OECD 24-28, 1996

19 J. Mahaffy, "Best Practice Guidelines for the Use of CFD in Nuclear Reactor Safety Applications" Nuclear Energy Agency of the OECD (NEA) 166-, 2007

20 N. Anderson, "Analysis of the hot gas flow in the outlet plenum of the very high temperature reactor using coupled RELAP5-3D system code and a CFD code" 238 : 274-279, 2008

21 D. L. Aumiller, "An integrated relap5-3d and multiphase cfd code system utilizing a semi-implicit coupling technique" 216 : 77-87, 2002

22 R. Bavi"ere, "A first system/CFD coupled simulation of a complete nuclear reactor transient using CATHARE2 and TRIO_U. Preliminary validation on the Ph"enix Reactor Natural Circulation Test" 277 : 124-137, 2014

23 D. Aumiller, "A Coupled RELAP5-3D/CFD Methodology with a Proof-Of-Principle Calculation, vol. 205"