Neutron irradiation embrittlement of reactor pressure vessel (RPV) steels is one of the important material ageing issues. The Japan Electric Association Code, JEAC 4201-2007 “Method of Surveillance Tests for Structur al Materials of Nuclear Reactors,” was revised in December 2007. A new mechanism-guided embrittlement correlation method was adopted. The surveillance program was modified for the long term operation of nuclear plan ts by introducing the “long-term surveillance program”, which is to be applied...
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Industry Practice for the Neutron Irradiation Embrittlement of Reactor Pressure Vessel Steels in Japan

One year has passed since Electronic Journal of Advanced Maintenance (EJAM) was started on the website of Japan Society of M aintenology (ISM) May 25“, 2009. “New Technology' (NT) is one of the EJAM categories, and introduces widely advanced techniqu es developed or modified for maintenance. Twenty-two NT articles have been introduced on EJAM website so far as of May 25t“, 2010. This report describes the concept of NT, general features of NT articles, actual performance and future wishes for NT....
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Current Status of EJAM ‘New Technology

1. はじめに 敦賀発電所敷地内 破砕帯評価について(続報) 日本原子力発電株式会社 堂﨑 浩二 Koji DOZAKI 日本原子力発電株式会社 入谷 剛 Takeshi IRIYA 日本原子力発電株式会社 牟田 隆司 Ryuji MUTA 前報 [1] では、日本原子力発電(以下、原電)敦賀発 電所敷地内破砕帯について、原子力規制委員会「敦賀発 電所敷地内破砕帯の調査に関する有識者会合」(以下、 有識者会合)が 2013 年 5 月 15 日における第 5 回評価会 合において、「耐震設計上考慮する活断......

Needs for development of practical technologies such as repair and mitigation, and necessity of conceptual summarization on those technologies are proposed. Temporary repair technology is focused in particular, to discuss its development needs for simple application and effectiveness for short period. Next, aggressive movements for standardization of allowable leak rules and repair technologies including the tentative ones in the United States are pointed out to find a promising orientation of utilizing...
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Needs for Temporary Repair Technology and Concept of Mitigation

Cracks were found at shroud support of Tokai II Power Station in 24th outage. Flaw evaluation of these cracks was performed applying Co des for Nuclear Power Generation Facilities - Rules on Fitness-for-Service ? (FFS Code) of Japan Society of Mechanical Engineers (JSME) and Guideline for Inspection and Evaluation of Reactor Internals of Japan Nuclear Technology Institute (JANTI). Evaluation methods and r esults are outlined in this report. Issues to be studied for better improvement of JSME FFS Code and J...
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Application of JSME Fitness-for-Service Code and JANTI Guideline for Inspection and Evaluation of ReactorInternals to Cracks found at Shroud Support of Tokai II Power Station

Inspection and Evaluation Guidelines for reactor internals has been taken into the Rules on Fitness-for-Service for Nuclear Power Plants of The Japa n Society of Mechanical Engineers. Now, It is a base of the maintenance plan of each Nuclear Power Plant. In the maintenance in the future, Inspecti on for the structures after repair, the replacement and the preventive maintenance becomes important. This paper introduces the systematization and the idea of the repair, the replacement and the preventive maint...
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The systematization and the idea of the repair, the replacement and the preventive maintenance in the Inspection and Evaluation Guidelines for Light Water Reactor Internals.

“The guideline committee for the inspection and evaluation of Reactor Vessel Internals” which was established in 2000 and transferred to Japan Nuclear Safety Institute in Nov.2012, developed many guidelines based on valid technical basis. These guidelines were made in principle which the conservative methodology, and covered both individual inspection method of reactor internals and application of repair methods for reactor internals. In this paper, overview of the activity is introduced. ...
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Outlines of Guidelines for the Inspection and Evaluation of Reactor Vessel Internals

Repair and Replacement Process (RRP) is one of the most important activities for maintenance of components or facilities in Nuclear Power Stations. Codes and Standards in RRP have been developed for a long time by some industrial organizations, such as Japan Power Engineering and Inspection Corporation (JAPEIC), Thermal and Nuclear Power Engineering Society (TENPES), Japan Nuclear Safety Institute (JANSI) and Japan Society of Mechanical Engineers (JSME). Though it seems to have some discussions for RR...
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Codes and Standards in Repair and Replacement Process: Needs and Uses

Working Group on Application Enhancement of Repair Replacement Technology has been established since September 2015, for the purpose of studying specific measures to create an environment that Japanese utilities can easily make corrective actions such as repair replacement technology applicable to Nuclear Power Plant to improve the safety of their own plants, and meetings have been held five times until the end of April 2016. In this paper, discussions on the WG meetings so far are shown, as well as th...
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Current Status of WG on Application Enhancement of Repair Replacement Technology