Loss of coolant accident research for PRC-2 triga reactor

机译：PRC-2三角反应堆失水事故研究

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This paper presents the characteristics of the PRC-2 TRIGA reactor. Loss of Coolant Accident (LOCA) analysis code (MCRLOCA code) and True Core Uncovered Model (TCUM). The main calculation schemes of LOCA research, calculation results, sensitivity analysis, safety evaluation and design improvement are also given in the paper.

机译：本文介绍了PRC-2 TRIGA反应器的特性。冷却剂事故（LOCA）分析代码（MCRLOCA代码）和True Core Uncovered Model（TCUM）丢失。本文还给出了LOCA研究的主要计算方案，计算结果，灵敏度分析，安全性评估和设计改进。

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《International topical meeting on nuclear thermal hydraulics, operations and safety;NUTHOS-5》|1997年|p.O8-1-5 ^b 5|共1页
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Wei Yongren; Tang Gang;
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中图分类原子能技术;
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专利

1. EVALUATION OF THE NEUTRONIC FEEDBACK EFFECTS IN LOSS OF COOLANT ACCIDENT SIMULATION OF THE IPR-R1 TRIGA REACTOR [J] . Patricia Amélia de Lima Reis, Antonella Lombardi Costa, Claubia Pereira, Computational thermal sciences . 2019,第3期

机译：评价IPR-R1 Triga反应器的冷却剂事故模拟中的中性反馈效应
2. Prediction of peak cladding temperature in a three-loop pressurised water reactor with accident- tolerant fuel during loss-of-coolant accident [J] . Alexander Agung International Journal of Nuclear Energy Science and Technology . 2018,第2期

机译：冷却液流失事故期间含事故容性燃料的三回路压水反应堆的最高包层温度预测
3. Analyses of loads on reactor pressure vessel internals in a pressurized water reactor due to a loss-of-coolant accident considering fluid-structure interaction [J] . P. Akimov, L. Obereisenbuchner Kerntechnik . 2010,第6期

机译：考虑流体-结构相互作用的冷却水损失事故导致压水反应堆中反应堆压力容器内部的载荷分析
4. Loss of coolant accident research for PRC-2 triga reactor [C] . Wei Yongren, Tang Gang International topical meeting on nuclear thermal hydraulics, operations and safety . 1997

机译：PRC-2 Triga反应堆冷却液事故研究的丧失
5. Experimental study of void behavior in a suppression pool of a boiling water reactor during the blowdown period of a loss of coolant accident. [D] . Rassame, Somboon. 2012

机译：冷却剂损失事故排污期间沸水反应堆抑制池中空隙行为的实验研究。
6. Development of underwater radiography scanner for reactor-pool experiment at the TRIGA PUSPATI reactor [O] . Mohamad Annuar Assadat Husain, Suhairul Hashim, Norasalwa Zakaria, 2018

机译：在TRIGA PUSPATI反应堆中进行反应堆池实验的水下射线照相扫描仪的开发
7. Loss of Coolant Accident (LOCA) / Emergency Core Coolant System (ECCS Evaluation of Risk-Informed Margins Management Strategies for a Representative Pressurized Water Reactor (PWR) [O] . Ronaldo Henriques Szilard 2016

机译：冷却液事故（LOCA）/紧急核心冷却液系统（ECCS对被告知的利润率的评估为代表加压水反应堆（PWR）
8. LOFA (Loss of Flow Accident) and LOCA (Loss of Coolant Accident) in the TIBER-II Engineering Test Reactor: Appendix A-4 [R] . Sviatoslavsky, I. N., Attaya, H. M., Corradini, M. L., 1987

机译：TIBER-II工程试验堆的LOFa（流量损失事故）和LOCa（冷却剂事故损失）：附录a-4

Loss of coolant accident research for PRC-2 triga reactor

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