Thermal-Hydraulic Transient Analyses for Primary Coolant System of HFRR Using RELAP5

被引：2

作者：

Veluri, Vijay K. ^{[1
]}

Sengupta, Samiran ^{[1
]}

机构：

[1] Bhabha Atom Res Ctr, Res Reactor Design & Projects Div, Mumbai, India

来源：

NUCLEAR TECHNOLOGY | 2023年 / 209卷 / 05期

关键词：

Fuel; loss-of-coolant accident; natural circulation valve; pump seizure; thermal hydraulics;

D O I：

10.1080/00295450.2022.2156245

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：

The High Flux Research Reactor (HFRR) is a 40 MW pool-type nuclear research reactor developed for neutron beam tube research, material and fuel irradiation studies, and advanced research using a cold neutron source. As a part of safety analyses, thermal-hydraulic transient analyses were carried out using the computer coder RELAP5 for the primary coolant system of the HFRR. This technical note presents various analyses that were carried out such as loss of normal electric power supply, loss of heat sink, main coolant pump seizure, inadvertent opening of a natural circulation valve, and loss-of-coolant accident considering breaks in the pump suction line and pump discharge line. It is demonstrated that fuel cooling is ensured and safety parameters are well within acceptable limits.

引用

页码：765 / 776

页数：12

共 15 条

[1] Code Development and Validation for Thermal-hydraulic Analysis of Helical Coil Steam Generator Based on RELAP5
Lian Q.
Tian W.
Qiu S.
Su G.
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2019, 53 (06): : 1007 - 1013
[2] Investigations of the VVER-1000 coolant transient benchmark phase 1 with the coupled system code RELAP5/PARCS
Espinoza, Sanchez
Hugo, Victor
Boettcher, Michael
PROGRESS IN NUCLEAR ENERGY, 2006, 48 (08) : 865 - 879
[3] ANALYSIS OF SYSTEM THERMAL-HYDRAULIC RESPONSES FOR PASSIVE SAFETY INJECTION EXPERIMENT AT ROSA-IV LARGE-SCALE TEST FACILITY - USING JAERI MODIFIED VERSION OF RELAP5/MOD2 CODE
ASAKA, H
YONOMOTO, T
KUKITA, Y
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1994, 31 (12) : 1265 - 1274
[4] Thermal hydraulic RELAP5 model for a solar direct steam generation system based on parabolic trough collectors operating in once-through mode
Serrano-Aguilera, J. J.
Valenzuela, L.
Parras, L.
ENERGY, 2017, 133 : 796 - 807
[5] Extension and application on a pool-type test facility of a system thermal-hydraulic/CFD coupling method for transient flow analyses
Toti, A.
Vierendeels, J.
Belloni, F.
NUCLEAR ENGINEERING AND DESIGN, 2018, 331 : 83 - 96
[6] Preliminary thermal-hydraulic analysis of the EU-DEMO Helium-Cooled Pebble Bed fusion reactor by using the RELAP5-3D system code
D'Amico, Salvatore
Di Maio, Pietro Alessandro
Jin, Xue Zhou
Gonzalez, Francisco Alberto Hernandez
Moscato, Ivo
Zhou, Guangming
FUSION ENGINEERING AND DESIGN, 2021, 162
[7] Safety Analysis in VVER-1000 due to Large-Break Loss-of-Coolant Accident and Station Blackout Transient using RELAP5/SCDAPSIM/MOD3.5
Thulu, Fabiano Gibson Daud
Elshahat, Ayah
Hassan, Mohamed
NUCLEAR SCIENCE AND ENGINEERING, 2022, 196 (05) : 568 - 583
[8] Feasibility study to increase the reactor power at natural convection mode in Tehran Research Reactor (TRR) through a hybrid thermal-hydraulic simulation and analysis using the RELAP5 code and Computational Fluid Dynamic (CFD) modeling by ANSYS-FLUENT
Hedayat, Afshin
Davari, Amin
PROGRESS IN NUCLEAR ENERGY, 2022, 150
[9] Transient characteristics of typical design basis accidents in integrated small reactor NHR200-II using RELAP5 model
Wang, Qian
Gui, Nan
Yang, Xingtuan
Tu, Jiyuan
Jiang, Shengyao
ANNALS OF NUCLEAR ENERGY, 2023, 192
[10] Thermal-hydraulic study of the Primary Heat Transport System of the EU-DEMO Divertor Plasma Facing Components
Vacca, S.
Agnello, G.
Bongiovi, G.
Castrovinci, F. M.
Chiovaro, P.
Di Maio, P. A.
Maviglia, F.
Moscato, I.
Quartararo, A.
Siccinio, M.
Vallone, E.
FUSION ENGINEERING AND DESIGN, 2024, 201

← 1 2 →