目　　次

■ 報　　告
圧延ラインを走行中の赤熱鋼管の肉厚測定 ( 3 )
門野浅雄 / 湯澤秀行 / 木村智充 / 金山太郎

■ 解　　説
J-PARC物質･生命科学実験施設における1MWパルス中性子源 ( 9 )
加藤　崇

■ 紹　　介
レーザー溶接法を用いたITERブランケット補修のための照射材接合試験 (16)
山田弘一 / 土谷邦彦
JAEA原子力科学研究所 環境放射線監視システムの開発 (21)
武原一記 / 佐々陽一 / 関田　勉
発電用新型炉へ適用する建屋全体３次元免震システムの開発 (30)
須原淳二 / 松本良一郎 / 大谷章仁 / 島田貴弘 / 井上和彦 / 生玉真也
高温構造設計における寿命評価法の課題と現状 (40)
島川貴司

■ グループ情報
FAPIGの機構 (52)

表紙デザイン：堀内秀和

CONTENTS

■ Report
Tube Wall Thickness Guage for Hot Stretch Reducer ( 3 )
A. Monno / H. Yuzawa / T. Kimura / T. Kanayama

■ Commentary
1MW Pulse Spallation Neutron Source at the Material
and Life Science Test Facility in J-PARC ( 9 )
T. Kato

■ Introduction
An Examination into Weldability of Irradiated Material
by a Laser Welding Method for Repair of ITER Blanket (16)
H. Yamada / K. Tsuchiya
Development of the New Environmental Radiation Monitoring System
in JAEA Nuclear Sciense Research Institute (21)
K. Takehara / Y. Sasa / T. Sekita
Development of Three-Dimensional Seismic Base Isolation
System Applied to Advanced Nuclear Power Plant (30)
J. Suhara / R. Matsumoto / A. Otani / T. Shimada / K. Inoue / S. Ikutama
Current Status and Issues on Creep-Fatigue Life
Evaluation in Elevated Temperature Design (40)
T. Shimakawa

Cover Design：Hidekazu Horiuchi

SYNOPSES

Asao Monno, Hideyuki Yuzawa, Tomomitsu Kimura, Taro Kanayama
Tube Wall Thickness Guage for Hot Stretch Reducer
FAPIG No. 173 pp.3〜8 (2006)

A new system of tube wall thickness gauge for seamless tube on hot stretch reducing-mill is reported.
The system adapts two methods using gamma rays.
One is a new method measuring double wall thickness of tube another is a known method measuring mean value of cross section of tube.

KEYWORDS：tube wall thickness, thickness gauge, seamless tube hot stretch reducer, gamma rays

Takashi Kato
1MW Pulse Spallation Neutron Source at the Material and Life Science Test Facility
in J-PARC
FAPIG No. 173 pp.9〜15 (2006)

Material and life science test facility is under the construction as a part of the Japan proton accelerator research complex (J-PARC) that utilizes an immense proton power (1-MW) accelerator. A 1-MW pulse spallation neutron source, that is the main facility at the material and life science test facility, is one of the world largest spallation neutron sources, utilizing a mercury target and liquid or supercritical hydrogen moderators. The neutron source has been designed and fabricated to exploit a state-of-the-art technology of the spallation neutron source engineering, expecting to produce one or two orders higher neutron intensity than that of the conventional neutron sources at the cold neutron regime.

KEYWORDS：J-PARC, neutron, spallation neutron source, cold neutron, mercury target, liquid/supercritical hydrogen moderator

Hirokazu Yamada, Kunihiko Tsuchiya
An Examination into Weldability of Irradiated Material by a Laser Welding Method
for Repair of ITER Blanket
FAPIG No. 173 pp.16〜20 (2006)

SS316L(N)-IG is the candidate material for the in-vessel and ex-vessel components of ITER (International Thermonuclear Experimental Reactor). This paper describes an examination into weldability of irradiated and un-irradiated SS316L(N)-IG for coolant piping, and investigation of the mechanical properties of welding joints as well as the effect of helium generation on weldability. A YAG laser welding process was used for repair welding of the water cooling branch pipelines. It was clarified that welding of SS316L(N)-IG irradiated up to 0.3 dpa (He content:about 3 appm) can be carried out without a significant deterioration of tensile properties due to helium accumulation. Therefore, repair of cooling pipes for the ITER blanket can be performed by the laser welding process.

KEYWORDS：ITER SUS316L(N)-IG, laser welding, neutron irradiation, helium generation, helium bubble

Kazuki Takehara, Youichi Sasa, Tsutomu Sekita
Development of the New Environmental Radiation Monitoring System
in JAEA Nuclear Science Research Institute
FAPIG No. 173 pp.21〜29 (2006)

Japan Atomic Energy Agency(JAEA)-Tokai Research and Development Center-Nuclear Science Research Institute observe the laws of radiation protection by the environmental monitoring and the meteorological observation around the nuclear facilities, counting and analyzing of its results, and report it to related organization.
On the purpose of efficiency of operation and improvement of the credibility of environmental surveillance works, they renewed the environmental radiation system in the fiscal year 2005 and have activated it since March 2006.
In this paper, we introduce the feature and the function of the new environmental radiation monitoring system.

KEYWORDS：environmental radiation monitoring, Japan Atomic Energy Agency, web based system, clustering technology, high availability

Junji Suhara, Ryoichiro Matsumoto, Akihito Otani, Takahiro Shimada, Kazuhiko Inoue, Shinya Ikutama
Development of Three-Dimensional Seismic Base Isolation
System Applied to Advanced Nuclear Power Plant
FAPIG No. 173 pp.30〜39 (2006)

Mitigation of the earthquake loads by seismic isolation technology is very promising for enhanced safety and economy of the next generation nuclear power plant. A research for 3D seismic isolation technology has been conducted under the sponsorship of the Ministry of Economy, Trade and Industry. Two types of 3D seismic isolation systems were developed. One is the 3D entire building base isolation system. The other is the vertical isolation system for main components in the horizontally entire building base isolation. For the former technology, the ﾒrolling seal type air spring + hydraulic rocking suppression systemﾓ is selected after several studies.
In this study, the reduced models of the 3D seismic base isolation system was tested on the shake tables. The test results show that this system satisfy the reliability of seismic isolation function and is applicable to the actual plant.

KEYWORDS：three-dimensional seismic isolation, fast breeder reactor, air spring, hydraulic mechanism, laminated rubber bearing, rocking suppression, shaking table test

Takashi Shimakawa
Current Status and Issues on Creep-Fatigue Life
Evaluation in Elevated Temperature Design
FAPIG No. 173 pp.40〜51 (2006)

Elevated temperature design standards have been developed in many countries to be applied for the designing of components operated at high temperature such as fossil power plant, petroleum plant and fast breeder reactor. Dominant failure mode considered in these components is creep-fatigue crack initiation under cyclic thermal stress at elevated temperature. It is important to develop the estimation methods for strain behavior and strength under the nonlinear conditions to perform a rational design. This paper presents a comparison among creep-fatigue life prediction methods in representative design codes such as ASME Sec. �VNH in USA, BDS and DDS in Japan, R5 in UK and RCC-MR in France.

KEYWORDS：elevated temperature design, creep-fatigue life, design standards