Improvement of Validation Technique for Long Term Soundness of In-core Component Materials of Light Water Reactor Plant after Repair and Maintenance

轻水堆核电站维修保养后堆芯部件材料长期完好性验证技术的改进

基本信息

批准号：
17360451
负责人：
HASEGAWA Akira
金额：
$ 10.43万
依托单位：
Tohoku University
依托单位国家：
日本
项目类别：
Grant-in-Aid for Scientific Research (B)
财政年份：
2005
资助国家：
日本
起止时间：
2005 至 2007
项目状态：
已结题

项目摘要

The objective of this study is to investigate damage microstructure development including He bubble formation in the austenitic stainless steel for in-core components including transmutant He atoms due to heat treatment during re-welding and neutron irradiation after rewelding by means of the simulation experiments using light ion implantation/irradiation by using an accelerator. The formation of He atoms was simulated using He ion implantation. The heat treatment during re-welding was simulated using a static heat treatment in a furnace.Damage microstructure development including helium (He) bubble formation in solution annealed type 316L austenitic stainless steel due to heat treatment (850 and 1050_oC for 5-500 min) after He ion pre-implantation (10-1000 appm) at room temperature and hydrogen (H) ion irradiation (0-0.5 dpa) at the temperature of 300_oC after the heat treatment was investigated in order to evaluate the microstructural degradation in a HAZ (heat affected zone) region … More of in-core components of fission reactors during re-welding and post welding neutron irradiation. The growth of He bubbles was observed due to the increment of He concentration, annealing time and annealing temperature of heat treatment, and displacement damage by H irradiation. He bubbles formed during the heat treatment and after H ion irradiation were distributed both in the grain boundary and in the matrix. The significant growth of He bubbles in the grain boundary after H irradiation up to 0.5 dpa was observed.It was clarified by this study that the growth of He bubbles significantly occurred due to the increment of He-concentration, annealing time and temperature of heat treatment, and displacement damage followed by He-ion implantation and heat treatment. He bubble formation in the grain boundary is well known to cause an embrittlement, weld metal cracking and degradation of weldability. Thus, in order to keep the highly reliable operation of fission reactor plants, the identifying the He concentration before re-welding repair, re-welding under the precisely controlled conditions, and the operation term and inspection periods after re-welding repair would be significantly important. Moreover, thermal stress and its cycling occurring due to the re-welding are also considered to cause the growth of He bubble. Therefore, the effect of thermal stress level and cycling on the He bubble formation and growth behavior must be investigated in future work. Less

这项研究的目的是研究损害微观结构的发展，包括在奥氏体不锈钢中发生气泡形成，用于核心成分，包括透射剂HE原子在重新焊接过程中由于热处理和中子辐射而通过使用轻度离子植入/辐照通过使用加速器进行仿真实验后的中性辐照后进行热处理。使用He离子植入模拟HE原子的形成。使用炉子中的静态热处理模拟了重新焊接过程中的热处理。损坏微观结构的开发，包括氦气（HE）气泡在溶液型316L型奥斯丁式不锈钢中，由于热处理（850和1050_OC）（850和1050_OC，用于5-500 min）在室内温度和水力发生（10-1000 appm）后（5-500 min）（室内温度下）（室内温度下）（室内温度下）（Hydrad）（室内温度下）（Hydrad）（Hydrad）Irrad（Hydrad）（H Hydrad）（H Hydrad）IINRAD（Hydrad）IINPA（Hyder inir in Inirogen（H）研究热处理后的300_oC温度，以评估HAZ（热影响区）区域中的微结构降解……在重新焊接和焊接后中子辐照过程中，更多的裂变反应器核内部成分。由于HE浓度的增加，退火时间和热处理的退火温度以及H辐射的位移损害，观察到HE气泡的生长。他在热处理期间形成的气泡和H离子照射后分布在晶界和基质中。 H辐射高达0.5 dPa后，HE气泡的显着增长被观察到。通过这项研究澄清，由于HE浓度的增加，热处理的退火时间和温度，HE气泡的生长显着发生，以及HE-ION植入和热处理。众所周知，他在晶界中的气泡形成会导致焊接性的封闭，焊接金属破裂和降解。为了保持裂变反应堆植物的高度可靠的运行，在重新焊接修复之前，在精确控制的条件下重新焊接的识别浓度以及重新焊接修复后的操作项和检查期很重要。此外，由于重新焊接而发生的热应力及其循环也被认为会导致HE气泡的生长。因此，必须在未来的工作中研究热应力水平和循环对HE气泡形成和生长行为的影响。较少的

项目成果

期刊论文数量（0）

专著数量（0）

科研奖励数量（0）

会议论文数量（0）

专利数量（0）

Study on Damage Analysis of Austenitic Stainless Steel for In-core Components of Fission Reactor using Accelerator Irradiation Experiments

裂变反应堆堆芯部件奥氏体不锈钢的加速器辐照实验损伤分析研究

DOI：
发表时间：
2008
期刊：
影响因子：
0
作者：
Masato Ito;Daigo Setoyama;Junji Matsunaga;Hiroaki Muta;Ken Kurosaki;Masayoshi Uno;Shinsuke Yamanaka;A. Hasegawa
通讯作者：
A. Hasegawa

照射損傷を受けた原子力用オーステナイトステンレス鋼におけるナノレベルの微細組織と変形組織の挙動解析

核奥氏体不锈钢辐照损伤纳米级显微组织和变形组织行为分析

DOI：
发表时间：
2007
期刊：
影响因子：
0
作者：
Masato Ito;Daigo Setoyama;Junji Matsunaga;Hiroaki Muta;Ken Kurosaki;Masayoshi Uno;Shinsuke Yamanaka;A. Hasegawa;A. Hasegawa;長谷川晃
通讯作者：
長谷川晃

水素イオン照射したオーステナイトステンレス鋼の照射誘起不均一変形挙動の評価

氢离子辐照奥氏体不锈钢辐照诱导异质变形行为评价

DOI：
发表时间：
2008
期刊：
影响因子：
0
作者：
Kazuo Takahashi;Masayoshi Uno;Mihoko Okui;Shinsuke Yamanaka;長谷川晃
通讯作者：
長谷川晃

Study on microstructure and deformation behavior of irradiated austenitic stainless steel

辐照奥氏体不锈钢显微组织及变形行为研究

DOI：
发表时间：
2007
期刊：
影响因子：
0
作者：
Masato Ito;Daigo Setoyama;Junji Matsunaga;Hiroaki Muta;Ken Kurosaki;Masayoshi Uno;Shinsuke Yamanaka;A. Hasegawa;A. Hasegawa;長谷川晃;A. Hasegawa
通讯作者：
A. Hasegawa

Study on Damage Microstructure Development of Re-welded Austenitic Stainless Steel of In-core Component Using Light-ion Irradiation

轻离子辐照核心部件重焊奥氏体不锈钢损伤微观组织发展研究