目　　次

■ 紹　　介
HTTRのI-I型材料照射試験用設備の開発 (3)
柴田大受 / 菊地孝行 / 宮本智司 / 小倉一知 / 石垣嘉信
軽水炉第一種機器構造健全性自動評価システムの開発 (8)
芦田拓己 / 中村協正 / 小川博志 / 小木曽誠太郎
よう素レーザによる原子炉解体技術の開発 (16)
月野徳之 / 和仁郁雄 / 尾角英毅 / 嶋田昌洋
伊崎　誠 / 原　邦男 / 宮尾英彦 / 中澤正治
極低溶出樹脂の開発 (23)
出水丈志 / 宮　茂夫 / 猪野隆夫 / 高井　寿 / 萩原正弘
マイクロ波による濃縮廃液のガラス化セメント固化技術の開発 (29)
藤沢盛夫 / 小原　潔 / 平野　貢 / 榊原康史
日本の電子行政の現状と動向 (32)
西田　徹

■ グループ情報
FAPIG第151〜160号総目次 (38)
FAPIGの機構 (48)

● Fresh Information（川崎重工） (22)

表紙デザイン：酒井美菜子

CONTENTS

■ Introduction
Development of the I-I type Irradiation Equipment for the HTTR (3)
T. Shibata / T. Kikuchi / S. Miyamoto / K. Ogura / Y. Ishigaki
Development of Integrated Assessment FEM Systems for LWR Class 1 Components (8)
T. Ashida / K. Nakamura /H. Ogawa /S. Ogiso
Development of Dismantling in Nuclear Reactor with Chemical Oxygen Iodine Laser (16)
N. Tsukino / F. Wani / H. Okado / M. Shimada / M. Izaki
K. Hara / H. Miyao / M. Nakazawa
A New Ion Exchange Resin with Minimized Production of Leachables
in Nuclear Power Plants (23)
T. Izumi / S. Miya / T. Ino / T. Takai / M. Hagiwara
Technology of Hardening Enriched Waste Liquid
with Vitrified Cement Using Microwaves (29)
M. Fujisawa / K. Obara / M. Hirano / Y. Sakakibara
Emerging Electoronic-Government Market (33)
T. Nishida

● Fresh Information (KAWASAKI HEAVY INDUSTRIES) (22)

Cover Design：Minako Sakai

SYNOPSES

Taiju Shibata, Takayuki Kikuchi, Satoshi Miyamoto, Kazutomo Ogura, Yoshinobu Ishigaki
Development of the I-I type Irradiation Equipment for the HTTR
FAPIG No. 161 pp.3〜7 (2002)

The I-I type irradiation equipment is the first irradiation rig for the HTTR. It will be served for the in-pile creep test for the standard size specimens of 316FR steel. Fabrication of the equipment was started in 1999. Its performances, such as the load transmission, temperature control and creep behavior measurement, were demonstrated outside the reactor in advance. It is now located temporally in the reactor building of the HTTR. After the demonstration of the performance of the HTTR, it will be installed in the reactor for the irradiation test.

KEYWORDS：HTTR, irradiation rig, in-pile creep test

Takumi Ashida, Kyotada Nakamura, Hiroshi Ogawa, Seitaro Ogiso
Development of Integrated Assessment FEM Systems for LWR Class 1 Components
FAPIG No. 161 pp.8〜15 (2002)

Structural integrity assessment for nuclear class 1 components in Light Water Reactor plant are performed based on “Design by Analyses” approach. In order to achieve the fatigue damage evaluation according to the Japanese structural integrity assessment code MITI501, the expert knowledge are widely required as for not only FEM modeling, know-how to using the FEM programs but theories about structural strength and the related assessment codes and standards.
　Authors have developed integrated assessment systems named "NuPIAS" for vessel, and "NuPIAS" for piping,respectively. These systems are realized as all in one PC systems by putting expertsﾕ knowledge together in systems and automating the complicated work steps.

KEYWORDS：Structural integrity assessment, MITI501, ReVIAS, NuPIAS, all in one PC systems

Noriyuki Tsukino, Fumio Wani, Hideki Okado, Masahiro Shimada, Makoto Izaki, Kunio Hara, Hidehiko Miyao, Masaharu Nakazawa
Development of Dismantling in Nuclear Reactor with Chemical Oxygen Iodine Laser
FAPIG No. 161 pp.16〜21 (2002)

The dismantling work of nuclear facilities for decommissioning requires the safe operation at the narrow space under highly radioactive condition. Therefore, the dismantling system is required to reduce the size of cutting devices and control remotely for safe operation. A remote cutting system with laser transmitted through optical fiber is promising the dismantling of nuclear facilities. The cutting system has been developed, and experimental study has been performed. Good results were obtained in the remote cutting test.

KEYWORDS：decommissioning, laser cutting, Chemical Oxygen Iodine Laser

Takeshi Izumi, Shigeo Miya, Takao Ino, Toshi Takai, Masahiro Hagiwara
A New Ion Exchange Resin with Minimized Production of Leachables in Nuclear Power Plants
FAPIG No. 161 pp.23〜28 (2002)

In nuclear power plants, the quality of the feed water should be kept very clean for minimizing the corrosion of the materials of the systems. One of the major impurities in the water is sulfate ion, which derives from the leachables from cation exchange resins being used in the condensate demineralizers. Therefore, reducing the amount of leachables from the resins is the utmost requirement in the power plants. In oreder to satisfy this requirement, the authors have developed the new cation exchange resin with high crosslinkages and uniform particle size distributions.
From the results of the oxidation treatment tests simulating the usage in the plants, the cation exchange resin with high crosslinkage has given the least leachables compared to the conventional resins. Furthermore, as the leachables from this resin has the lowest molecular weight distribution, it affected the anion resin kinetics least. On the other hand, the high crosslinkage resin are said to have poorer kinetics and regeneration efficiency. We have evaluated that it has similar kinetics and slightly poorer regeneration efficiency and confirmed that they are practically no significant problems on the plant usage.

KEYWORDS：ion exchange resin, high crosslinkage, condensate demineralizers, leachables, cation exchange resin, molecular weight distribution, kinetics, regenerating characteristics, water retention capacity, leaching rate of TOC

Morio Fujisawa, Kiyoshi Obara, Mitsugu Hirano, Yasushi Sakakibara
Technology of Hardening Enriched Waste Liquid with Vitrified Cement Using Microwaves
FAPIG No. 161 pp.29〜32 (2002)

Radioactive wastes are generated from those facilities that handle radioactive substances including nuclear power plants and usually such wastes are subjected to the volume reduction process and then subjected to the hardening process for stabilization and/or disposition. Among other radioactive wastes as the object of the hardening process, hardening with asphalt, hardening with plastics, and hardening with cement have so far been implemented for enriched waste liquid. However, in connection with the commencement of disposal by laying underground in Shimokita, a higher volume reduction rate than that in existing technologies has come to be required. Therefore, Fuji Electric Co., Ltd. has developed technology of hardening enriched waste liquid with vitrified cement using microwaves

KEYWORDS：microwave, vitrification, hardening with cement, volume reduction, boric acid

Tohru Nishida
Emerging Electoronic-Government Market
FAPIG No. 161 pp.33〜37 (2002)

According as the rapid spread of Internet users, a lot of IT policies have been carried out from some ministry.
In 2001, the basic low on the formation of an advanced information telecommunications network society come into force, and also "e-Japan Priority Policy Program" was announced by the Government. "e-Japan Priority Policy Program" is the basic IT policy of Japan, aimed at world's most advanced IT nation within five years.
In March 2001, the IT Strategy Headquarters announced the "e-Japan Priority Policy Program" and started to tackle the implementation of Electronic Government. Electronic Government is one of four priorities policy areas identified in the "e-Japan Strategy". Electronic Government will be conducted online, not only administrative transactions among government offices ("G to G") but also those transactions between government and citizens or between government and businesses ("G to C" or "G to B"). The goal is to make the public administration process simpler and more efficient, and to lessen the burden on citizens and businesses.

KEYWORDS：IT Strategy Head quarters , Electronic Government, "e-Japan Priority Policy Program", "G to C", "G to C", "G to B", IT policies, ministry