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Application of Reliability Techniques to Prioritize BWR (Boiling Water Reactor) Recirculation Loop Welds for In-Service Inspection.

机译：可靠性技术在BWR（沸水反应堆）再循环回路焊接在役检测中的应用。

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Analytical predictions of pipe damage at Carolina Power & Light Company's Brunswick plant were compared with observed damage, using the recirculation loop piping. The probabilistic fracture mechanics calculations generally compared well with actually occurring phenomena.

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作者
Holman, G. S.;
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年度 1989
页码 1-74
总页数 74
原文格式 PDF
正文语种 eng
中图分类工业技术;
关键词
BWR type reactors; Piping systems; Fracture mechanics; Reliability; Inspection; Reactor cooling systems; Weldments; Stress corrosion; Cracks; Steels; PRAISE computer program; Recirculation pipes; In service inspection;

机译：BWR型反应器;管道系统;断裂力学;可靠性;检查;反应堆冷却系统;焊件;应力腐蚀;裂缝;钢; pRaIsE计算机程序;再循环管道;在役检查;

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1. Extending the reactivity initiated accident (RIA) fuel performance code SCANAIR for boiling water reactor (BWR) applications [J] . Arkoma Asko Nuclear Engineering and Design . 2017,第octa期

机译：将反应性引发事故（RIA）燃料性能代码SCANAIR扩展到沸水反应堆（BWR）应用中
2. Hydride Embrittlement and Irradiation Effects on the Hoop Mechanical Properties of Pressurized Water Reactor (PWR) and Boiling-Water Reactor (BWR) ZIRCALOY Cladding Tubes: Part III. Mechanical Behavior of Hydride in Stress-Relieved Annealed and Recry [J] . SYLVIE ARSENE, JINBO BAI, PHILIPE BOMPARD Metallurgical and Materials Transactions, A. Physical Metallurgy and Materials Science . 2003,第3期

机译：氢化物脆化和辐射对压水反应堆（PWR）和沸水反应堆（BWR）ZIRCALOY熔覆管箍力学性能的影响：第三部分。氢化物在消除应力的退火和回填中的力学行为
3. Hydride Embrittlement and Irradiation Effects on the Hoop Mechanical Properties of Pressurized Water Reactor (PWR) and Boiling-Water Reactor (BWR) ZIRCALOY Cladding Tubes: Part I. Hydride Embrittlement in Stress-Relieved, Annealed, and Recrystallized [J] . S. ARSENE, J.B. BAI, P. BOMPARD Metallurgical and Materials Transactions, A. Physical Metallurgy and Materials Science . 2003,第3期

机译：加压水反应器（PWR）和沸水反应器（BWR）ZIRCALOY覆层管中的氢化物脆化和辐照对箍力学性能的影响：第一部分。应力消除，退火和重结晶中的氢化物脆化
4. The coolant in boiling water reactors (BWRs) recirculation lines is high purity,neutral pH water containing radiolytically generated O_2,H_2O_2 and H_2.The level of the oxidant is sufficient to promote intergranular stress corrosion cracking (IGSCC) [C] . L.M.Santiso, J.Abella, L.Victori The Meeting of the Electrochemical Society . 2002

机译：沸水反应器（BWR）再循环管线中的冷却剂是高纯度，中性pH水含有放射性地产生的O_2，H_2O_2和H_2。氧化剂的水平足以促进晶间应力腐蚀裂纹（IGSCC）
5. Neutron transport with the method of characteristics for 3-D full core boiling water reactor applications. [D] . Thomas, Justin W. 2006

机译：具有3-D全芯沸水反应堆应用特征方法的中子传输。
6. Leukemia in the proximity of a German boiling-water nuclear reactor: evidence of population exposure by chromosome studies and environmental radioactivity. [O] . I Schmitz-Feuerhake, B Dannheim, A Heimers, 1997

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7. REACTOR PHYSICS CALCULATIONS ON MOX FUEL IN BOILING WATER REACTORS (BWRs) [O] . Christophe Demazière 2012

机译：沸水反应堆（BWRs）mOX燃料的反应物理计算
8. Radionuclide Buildup in BWR (Boiling Water Reactor) Reactor Coolant Recirculation Piping. [R] . Duce, S. W., Marley, A. W., Freeman, A. L. 1989

机译：BWR（沸水反应堆）反应堆冷却剂再循环管道中的放射性核素积累。

Application of Reliability Techniques to Prioritize BWR (Boiling Water Reactor) Recirculation Loop Welds for In-Service Inspection.

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