Verification of Neutronics and Thermal-hydraulics Coupled Simulation Program NTC by the PDS-XADS transient simulation

被引：5
|
作者：
Wang, Gang [1 ]
Gu, Zhixing [1 ,2 ]
Wang, Zhen [1 ,2 ]
Jin, Ming [1 ]
机构：
[1] Chinese Acad Sci, Inst Nucl Energy Safety Technol, Key Lab Neutron & Radiat Safety, Hefei 230031, Anhui, Peoples R China
[2] Univ Sci & Technol China, Hefei 230027, Anhui, Peoples R China
来源：
PROGRESS IN NUCLEAR ENERGY | 2015年 / 85卷
关键词：
PDS-XADS; Verification; NTC; Neutronics and thermal-hydraulics coupling; Transient analysis; ACCELERATOR-DRIVEN SYSTEM; TEST BLANKET MODULE; SIMMER-III CODE; CONCEPTUAL DESIGN; MATERIAL SELECTION; REACTOR; CHINA; ACCIDENT; STRATEGY; ITER;
D O I：
10.1016/j.pnucene.2015.08.013
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：
In this paper, the steady state and three typical transient accidents of LBE-cooled sub-critical experimental accelerator driven system reactor were simulated by the Neutronics and Thermal-hydraulics Coupled Simulation Program (NTC) developed by FDS team. The three transient accidents were beam trip (BT), unprotected beam overpower (UBOP) and unprotected transient overpower (UTOP). The NTC-based simulation results of PDS-XADS were compared with those based on SIMMER-III, and the simulation and comparison results showed that the trends of all the neutronics and thermal-hydraulics parameters of NTC-based simulations in this study were similar and close to those of SIMMER-III-based simulation results, which verified the simulation capacity and correctness of NTC code in a manner. (C) 2015 Elsevier Ltd. All rights reserved.
引用
收藏
页码：659 / 667
页数：9
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