Vessel Investigation Program of 'CHOOZ A' PWR Reactor after Shutdown

机译：“ CHOOZ A”压水堆关闭后的船舶调查程序

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In October 1991 the CHOOZ A PWR plant, operated by the French and Belgian company SENA, was shut down after 24 years. It was the first PWR shutdown in France. According to the EDF life duration project it was decided to perform an examination program on samples taken from the wall of the vessel in order to complete the feedback. The results obtained show the following: 1. The embrittlement measured by the pressure vessel surveillance program is representative of that of the Shell determined at different axial and angular locations for the 1/4 of the internal thickness. This observation is consistent with the relative homogeneity of the embrittling elements (Cu, P, Ni) throughout the entire Shell, 2. The mechanical properties evolution through the wall thickness of the Shell measured after irradiation is interpreted in relation with fluence variation and unirradiated mechanical properties profile through the thickness, 3. The comparison of direct toughness measurement with the French code RCC-M evaluation confirms the safety nature of the conventional approach. For the weld, after an irradiation damage of 2 10~(19) n.cm~(-2) (E>lMeV), a margin of the order of the irradiation effect seems to exist.

机译：1991年10月，由法国和比利时SENA公司运营的CHOOZ A PWR工厂关闭了24年。这是法国首次关闭压水堆。根据EDF寿命项目，决定对从容器壁上采集的样品执行检查程序，以完成反馈。获得的结果表明：1.压力容器监控程序测得的脆化代表了壳在不同轴向和角位置处（对于内部厚度的1/4）确定的脆化。该观察结果与整个壳体中脆化元素（Cu，P，Ni）的相对均匀性是一致的。2.辐照后测得的整个壳体壁厚的机械性能演变与注量变化和未辐照机械有关厚度方向的特性曲线。3.直接韧性测量与法国规范RCC-M评估的比较证实了常规方法的安全性。对于焊缝，在2 10〜（19）n.cm〜（-2）（E> lMeV）的辐照损伤后，似乎存在辐照效应量级的余量。

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来源
《20th International Symposium on Effects of Radiation on Materials, Jun 6-8, 2000, Williamsburg, Virginia》|2000年|p.28-41|共14页
会议地点 Willamsburg(GB)
作者
Christian Brillaud; Yves Grandjean; Sebastien Saillet;
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作者单位

Electricite de France, Industry Branch, Nuclear Production Division, Corporate Laboratories, GDL Chinon, B.P. 23, Avoine, France;

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会议组织
原文格式 PDF
正文语种 eng
中图分类原子能技术;
关键词
fracture toughness; charpy; transition; reactor pressure vessel steel; reference temperature; master curve; irradiation; reactor shutdown;

机译：断裂韧性夏比过渡;反应堆压力容器钢；参考温度主曲线辐照反应堆关闭;

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1. MCNP Neutron Streaming Investigations from the Reactor Core to Regions Outside the Reactor Pressure Vessel for a Swiss PWR [J] . Ben Volmert, Elena Tamaseviciute, Manuel Pantelias, Transactions of the American nuclear society . 2013,第novapta2期

机译：瑞士压水堆从反应堆堆芯到反应堆压力容器以外区域的MCNP中子流研究
2. Investigation of alternative solutions for PWR severe accident management: Objectives of the CEA 'Innovations - Future reactors' Program [J] . P. RAYMOND, I. SZABO Revue generale nucleaire . 1997,第期

机译：研究压水堆严重事故管理的替代解决方案：CEA“创新-未来反应堆”计划的目标
3. An assessment methodology for in-vessel corium retention by external reactor vessel cooling during severe accidents in PWRs [J] . Jae Hong Park, Yong Hoon Jeong, Won-Pil Baek Annals of nuclear energy . 2001,第12期

机译：在压水堆严重事故期间通过外部反应堆容器冷却来保留在容器中的钙的评估方法
4. Vessel Investigation Program of "CHOOZ A" PWR Reactor after Shutdown [C] . Christian Brillaud, Yves Grandjean, Sebastien Saillet, Symposium on effects of radiation on materials . 2001

机译：关闭后“Chooz A”PWR反应器的船舶调查计划
5. INVESTIGATION OF OPTIMAL REACTOR CONTROL FOR A LOAD-FOLLOWING PWR. [D] . YIM, MAN-SUNG. 1987

机译：负荷跟踪压水堆最佳反应堆控制的研究。
6. Discovery of fissionogenic Cs and Ba capture five years after Oklo reactor shutdown [O] . Evan E. Groopman, David G. Willingham, Alex P. Meshik, 2018

机译：Oklo反应堆关闭五年后发现了会产生裂变的Cs和Ba
7. Radioactive Gaseous Behavior in the PWR Primary Coolant System : Remoral of Hydrogen and Radioactive Rare Gas at Reactor Shutdown [O] . Hideo YOSHIKAWA, Masaharu KORI 1984

机译：PWR初级冷却剂系统中的放射性气态行为：反应器关断的氢气和放射性稀有气体的伴随
8. Investigating the Flux-Reduction Option in Reactor-Vessel Integrity (PWR) [R] . Franklin, D., Marston, T. 1983

机译：研究反应堆容器完整性（pWR）中的流量减少选项

Vessel Investigation Program of 'CHOOZ A' PWR Reactor after Shutdown

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