低温低压试验回路辐照钼锝同位素安全研究

张毅; 徐西安; 张培升

doi:10.7538/yzk.2020.youxian.0801

低温低压试验回路辐照钼锝同位素安全研究

中国原子能科学研究院反应堆工程技术研究部,北京102413

计量
- 文章访问数: 68
- HTML全文浏览量: 0
- PDF下载量: 809
出版历程
- 刊出日期: 2021-06-19

Safety Research on Mo-Tc Isotope Irradiation with Low Temperature and Low Pressure Test Loop

Division of Reactor Engineering Technology Research, China Institute of Atomic Energy, Beijing 102413, China

摘要

摘要: 钼锝同位素是一种重要的医用同位素，铀-235在低温低压堆内试验回路中进行辐照是钼锝同位素生产的一种重要方法。为了确保钼锝同位素辐照过程不会危及试验回路、研究堆的安全，建立了回路的RELAP5模型，并对钼锝同位素生产进行安全分析研究。分析结果表明，即使辐照过程中发生了典型的设计基准事故，也不会对靶件、试验回路及反应堆构成威胁，辐照过程符合安全要求。
- 试验回路 ,
- 堆内辐照 ,
- 事故分析 ,
- 钼锝同位素
Abstract: Mo-Tc isotope is an important medical isotope. The irradiation of ²³⁵U in the low-temperature and low-pressure in-core test loop is an important method for Mo-Tc isotope production. In order to ensure the test loop and reactor are safe in the irradiation process of Mo-Tc isotope, the RELAP5 model of the loop was developed and the safety analysis was performed on the production of Mo-Tc isotope with the low-temperature and low-pressure test loop. The calculated results show that the Mo-Tc isotope irradiation process will not endanger the safety of the test loop and the research reactor, and the safety requirements are met during a typical design basis accident.
- test loop ,
- in-reactor irradiation ,
- accident analysis ,
- Mo-Tc isotope

HTML全文

参考文献(16)

[1]	IAEA. NF-T-5.4Non-HEU production technologies for molybdenum-99 and technetium-99m[S]. US: IAEA, 2013.
[2]	尹志民，韩耀礼，张品源，等. ⁹⁹Mo-⁹⁹Tc^m同位素辐照靶件研制[J]. 原子能科学技术,1986,20（2）:129-135. YIN Zhimin, HAN Yaoli, ZHANG Pinyuan, et al. The preparation of irradiation of ⁹⁹Mo-⁹⁹Tc^m isotope production[J]. Atomic Energy Science and Technology, 1986, 20（2）: 129-135（in Chinese）.
[3]	唐学人，吕光全，林璋,等. 5 MW低功率反应堆[J]. 核动力工程,1992,13（4）:2-6. TANG Xueren, LV Guangquan, LIN Zhang, et al. 5 MW low power reator[J]. Nuclear Power Engineering, 1992, 13（4）: 2-6（in Chinese）.
[4]	朱继洲. 核反应堆安全分析[M]. 西安：西安交通大学出版社，2000:80-140.
[5]	张世顺. 堆内试验回路事故安全分析[J]. 核动力工程,1994,15（5）:436-439. ZHANG Shishun. Accident safety analyses for in-pile test loops[J]. Nuclear Power Engineering, 1994, 15（5）: 436-439（in Chinese）.
[6]	张述诚. 秦山核电站堆内考验PWR燃料棒束安全分析[R]. 北京：中国原子能科学研究院，1984.
[7]	王红兵，金华晋. 高温高压及低温低压辐照组件的物理设计[R]. 北京：中国原子能科学研究院，1992.
[8]	张世顺. 低温低压试验回路热工水力安全分析[R]. 北京：中国原子能科学研究院，1992.
[9]	张森如. 金山核热电站一回路失流事故分析[J]. 核动力工程,1986,7（2）:21-28. ZHANG Senru. Loos of primary loop flow accident analysis for Jinshan[J]. Nuclear Power Engineering, 1986, 7（2）: 21-28（in Chinese）.
[10]	张沿发，张维中. 秦山核电厂一回路惰走流量测量[J]. 核动力工程,1993,14（5）:394-396. ZHANG Yanfa, ZHANG Weizhong. Measurement of the coastdown flowrate for QinShan Nuclear Power Plant[J]. Nuclear Power Engineering, 1993, 14（5）: 394-396（in Chinese）.
[11]	张毅,季松涛. 秦山二期核电站环形燃料堆芯卡轴及弹棒事故分析[J]. 原子能科学技术,2016,50（11）:314-317. ZHANG Yi, JI Songtao. Analysis of locked-rotor accident and rod ejection accident for Qin-shan Phase Ⅱ Nuclear Power Plant with annular fuel[J]. Atomic Energy Science and Technology, 2016, 50（11）: 314-317（in Chinese）.
[12]	张毅,季松涛，张应超. CARR高温高压试验回路小破口失水事故分析[J]. 原子能科学技术,2007,41(增刊):314-317. ZHANG Yi, JI Songtao, ZHANG Yingchao. Analysis on CARR high-temperature and high-pressure loop SBLOCA[J]. Atomic Energy Science and Technology, 2007, 41(Suppl.): 314-317（in Chinese）.
[13]	汪景新，赵华，王开明. 4×4燃料组件考验装置小破口失水事故分析[J]. 核动力工程,1999,20（4）:299-332. WANG Jingxin, ZHAO Hua, WANG Kaiming. Supplementary analysis of small break loss of coolant accident on 4×4 fuel-assemble tests[J]. Nuclear Power Engineering, 1999, 20（4）: 299-332（in Chinese）.
[14]	张毅,季松涛. 秦山二期核电站采用环形燃料LBLOCA研究[J]. 原子能科学技术,2014,48(增刊):50-53. ZHANG Yi, JI Songtao. Study on LBLOCA of Qinshan Phase Ⅱ Nuclear Power Plant project loaded with annular fuel[J]. Atomic Energy Science and Technology, 2014, 48(Suppl.): 50-53（in Chinese）.
[15]	博金海，王飞. 小破口失水事故研究综述[J]. 核科学与工程, 1998,18（2）:172-179. BO Jinhai, WANG Fei. Review on research of small break loss of coolant accident[J]. Chinese Journal of Nuclear Science and Engineering, 1998, 18（2）: 172-179（in Chinese）.
[16]	余红星，廖业宏. 中小破口失水事故现实估算分析[J]. 核动力工程,2002,23（5）:37-39. YU Hongxing, LIAO Yehong. Realistic analysis of intermediate and small LOCA[J]. Nuclear Power Engineering, 2002, 23（5）: 37-39（in Chinese）.

施引文献

资源附件(0)

计量

文章访问数: 68
HTML全文浏览量: 0
PDF下载量: 809
被引次数: 0

低温低压试验回路辐照钼锝同位素安全研究

计量

出版历程

Safety Research on Mo-Tc Isotope Irradiation with Low Temperature and Low Pressure Test Loop

计量

出版历程

目录