FAPIG

THE FlRST ATOMlC POWER INDUSTRY GROUP

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FAPIGŽ@ÅV†–ÚŽŸ

2007|2/•½¬18”N“x@‘æ‚Q†(No.174)

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CONTENTS

¡ Essay
All Efforts for HTGR Thrive at Thrice (3)
K. Sato

¡ Report
Present Status of Proto-type FBR MONJU (5)
Progress of Construction Work for Sodium Leak Event and Preparation of Re-operation
N. Uchiyama
Engineering Study on Dismantling of Steam
Raising Unit in Tokai Power Station (11)
S.Takenaka / H. Kimura / K. Tokieda / T. Hirahashi / S. Yamazaki

¡ Introduction
The Present Status of HTGR Developments in the World (19)
M. Nakano / E. Takada / F. Okamoto
Development of Radiation Transmission Type Pipe Wall Thinning Detection System (26)
A. Takagi
Research • Development for Construction of
gComputational Infrastructure in Atomic Energy Research Fieldh
Based on Grid Computing Technology (31)
T. Minami / Y. Suzuki / T. Aoyagi / T. Ito / N. Nakajima

¡ Paper
Development of Radioactive Spent Ion-exchange Resin Treatment System (40)
T. Izumi / M. Hagiwara / T. Ohtsu / M. Tsujita
M. Arai / H. Inagawa / M. Noumi

¡ FAPIG Activities
FAPIG's Activities for Public Acceptance of Nuclear Energy (43)
M. Yoneda

Cover DesignFHidekazu Horiuchi

 

SYNOPSES

Naoki Uchiyama
Present Status of Proto-type FBR MONJU
Progress of Construction Work for Sodium Leak Event and Preparation of Re-operation
FAPIG No. 174 pp.5`10 (2007)

The operation of Proto-type Fast Breeder Reactor MONJU has been suspended since December 1995, due to the sodium leak accident at the secondary cooling system. The construction work for sodium leak event is progressing from September 2005, to solve the problems pointed out in the general safety investigation of MONJU carried out after this accident. 90% of the construction work was completed at the end of December 2006. The confirmation test was already started from December 18, 2006.
This report describes the present status of MONJU, mainly about the progress and results of the construction work performed by Kawasaki Plant Systems, Ltd. and Fuji Electric Systems Co., Ltd.

KEYWORDSFproto-type, FBR, fast breeder reactor, MONJU, sodium leak accident, construction work

Satsuki Takenaka, Hideaki Kimura, Kiyoshi Tokieda, Tsuyoshi Hirahashi, Seiichiro Yamazaki
Engineering Study on Dismantling of Steam Raising Unit in Tokai Power Station
FAPIG No. 174 pp.11`18 (2007)

Tokai Power Station (TPS) of The Japan Atomic Power Company (JAPC) started the commercial operation in 1966. JAPC is now dismantling by themselves after the commercial operation stop in 1998. Kawasaki Plant Systems, LTD (K Plant) took part in the construction of TPS and manufactured and maintained its primary system including the heat exchangers (SRU). And K-Plant had investigated the decommissioning methods with JAPC.
Dismantling of TPS has been started from 2001, and the dismantling of equipments around SRU from 2006. SRU is the largest sized components after reactor vessel and makes primary loop boundary. It is important that preventing contamination spread should be considered because inside of SRU is contaminated. JAPC and K-Plant have achieved that SRUs should be dismantled by jack-down method because of preventing radioactive materials diffusion and keeping safety.
This report shows the plan of SRU dismantling.

KEYWORDSFnuclear power station, decommissioning, dismantling, steam raising unit

Masaaki Nakano, Eiji Takada, Futoshi Okamoto
The Present Status of HTGR Developments in the World
FAPIG No. 174 pp.19`25 (2007)

High temperature gas-cooled reactors (HTGR) have superior potential for both electricity and hydrogen production due to the high outlet temperature. In this paper, present status of developments of HTGR are summarized for Japan, USA, China, South Africa, France and Korea.

KEYWORDSFHTGR, HTR, GIF, VHTR

Akira Takagi
Development of Radiation Transmission Type Pipe Wall Thinning Detection System
FAPIG No. 174 pp.26`30 (2007)

We, based on the joint study with Tohoku Electric Power Co., Ltd, developed the device to detect wastage of pipe thorough heat insulation in Power Plant, etc, even while the plant is under operation.
It is necessary to test many parts of many pipes within a limited time of the routine test.
This device consists of detector and radiation source, which can detect the pipe (less than 500mm in external diameter, less than 50mm in thickness) with 1.6“-reproducibility (in a few-minutes measurement), based on the transmission rate.
Operation is easy and effective without removing the heat insulation.
We will expand this wastage detection system, and contribute the safety of the Plant.

KEYWORDSFwastage of pipe, detection thorough heat insulation, based on the trans-mission of radiation, safety of plants

Takahiro Minami, Yoshio Suzuki, Tetsuo Aoyagi, Toshinori Ito, Norihiro Nakajima
Research & Development for Construction of "Computational Infrastructure in Atomic Energy Research Field" Based on Grid Computing Technology
FAPIG No. 174 pp.31`39 (2007)

The Center for Computational Science and E-systems of the Japan Atomic Energy Agency (CCSE/JAEA) has started a program to construct an international computational infrastructure in atomic energy research field called the AEGIS (Atomic Energy Grid InfraStructure) in April, 2006. The development is based on numerous experiences and technologies acquired from the development of the STA (Seamless Thinking Aid) and the ITBL (Information Technology Based Laboratory) infrastructure software. In this paper, we will introduce two key achievements prior to the AEGIS program: ÒInteroperable system between UNICORE in Germany and ITBLÓ which achieves international sharing of computational resources, and the "STARPC Plus" which can construct a compact grid system.

KEYWORDSFjapan atomic energy agency, computational infrastructure, atomic energy grid infrastructure, seamless thinking aid, information technology based laboratory, uniform interface to computing resources, interoperation, international sharing, computational resource, grid system

Takeshi Izumi, Masahiro Hagiwara, Takashi Ohtsu, Masaharu Tsujita, Masayuki Arai, Hirofumi Inagawa, Mitsuhiko Noumi
Development of Radioactive Spent Ion-exchange Resin Treatment System
FAPIG No. 174 pp.40`42 (2007)

In nuclear power plants, ion exchange resins are used at water purification systems such as condensate demineralizers. After usage, used ion exchange resins are stored at plants as low level radioactive wastes. Ion exchange resins contain water and so, those are flame resistant materials. At present, ion exchange resins are incinerated with other inflamable materials at incinerators. Furthermore, ion exchange reisns are fine perticle beads and are easy to be scattered in all directions, so operators must pay attentions for treatment.
Then, we have developed the new solidification system of ion exchange resins with paraffin wax. Ion exchange resins are mixed and extruded with paraffin wax and these solids are enable to incinerate at existing incinerators.

KEYWORDSFnuclear power plants, ion exchange resins, radioactive wastes, incineration treatment, solidification

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