乗松　孝好
大阪大学レーザー核融合研究センター
〒565　吹田市山田丘2-6

T. NORIMATSU
Institute of Laser Engineering, Osaka University,2-6, Yamada-oka, Suita, Osaka 565, JAPAN
(Received September 4, 1995; accepted January 22, 1996)

Abstract
　After achieving high temperature and high density compression, laser fusion research proceeded to a new stage to demonstrate ignition and burning of the compressed fuel. In these experiments, high spherical symmetry is required for implosion and target techniques including shell fabrication, cryogenic technologies and tritium handing are again going to play an important role with irradiation uniformity of the main laser. The present status and requirements for the target are discussed with cryogenic technologies and tritium technologies being centered on.

河村　弘、佐川　尚司、石塚　悦男、土谷　邦彦,　中道　勝、堀井　一宏、坂本　直樹、新保　利定
日本原子力研究所　大洗研究所
〒311-13　茨城県東茨城郡大洗町成田町新堀3607

Hiroshi KAWAMURA, Hisashi SAGAWA, Etsuo Ishitsuka, Kunihiko TSUCHIYA, Masaru NAKAMICHI,Kazuhiro HORII, Naoki SAKAMOTO, Toshisada Niiho
Oarai Research Establishment Japan Atomic Energy Research Institute
3607 Shinbori, Natita-cho, Oarai-machi, Higashi-ibaraki-gun, Ibaraki-ken, JAPAN

Abstract
　Components such as a blanket or divertor and instruments are exposed to a severe neutron irradiation field. As regards engineering, it is needed to grasp the characteristics of the components and instruments under neutron irradiation. Especially, a fusion blanket is the center of components, because it breeds tritium, generating heat energy and shielding neutron. Therefore, it is necessary to evaluate the in-pile functions of the blanket under neutron irradiation so as to construct ITER.
  JMTR of the Oarai Establishment at JAERI is conducting in-pile functional tests of a blanket mock-up, the development of blanket materials, the development of instruments, a re-weldability test for vacuum vessel materials, an electron beam irradiation test of the divertor and armor materials after neutron irradiation and so on. This report briefly describes the present status of each study.

小林　徹^*1、松山　政夫^*2、渡辺　国昭^*2、田口　茂^*1
*1富山大学理学部
^*2富山大学　水素同位体機能研究センター
〒930富山市五福3190

Tohru KOBAYASHI^*1, Masao MATSUYAMA^*2, Kuniaki WATANABE^*2, Shigeru TAGUCHI^*1
*1Faculty of Science, Toyama University
^*2Hydrogen Isotope Research Center, Toyama University
Gofuku 3190, Toyama 930, JAPAN
(Received October 13, 1995; accepted December 22, 1995)

Abstract
　To improve hydrogen isotope separation by chromatography, a study was carried out to develop a new type of replacement chromatography working near room temperature. For this purpose, a Pd-Pt alloy way selected. It was revealed that it could separate a 50%H₂-50%D₂ mixture gas to H₂ and D₂ near room temperature without bringing in any replacement gas. This was then denominated as “self-developing replacement chromatography”. The separation efficiency, however, was varied with operating conditions such as temperature and flow rate, but did not depend very much on the amount of sample gas. Factors affecting the separation efficiency were discussed.

芦田　完^*1、渡辺　国昭^*1、江角　直道^*2、岡部　俊夫^*2、河村　弘^*3
*1富山大学水素同位体機能研究センター
^*2富山大学理学部物理学科
〒930　富山市五福3190
^*3日本原子力研究所大洗研究所
〒311-13　茨城県東茨城郡大洗町

Kan ASHIDA^*1, Kuniaki WATANABE^*1, Naomichi EZUMI^*2, Toshio OKABE^*2, and Hiroshi KAWAMURA^*3
*1Hydrogen Isotope Research Center, Toyama University
^*2Faculty of Science, Department of Physics, Toyama University
Gofuku 3190, Toyama 930, JAPAN
^*3Japan Atomic Energy Research Institute (JAERI), Oarai Establishment
3607 Shinbori, Narita-cho, Oarai-machi, Higashi-ibaraki-gun, Ibaraki 311-13, JAPAN
(Received October 9, 1995; accepted December 22, 1995)

Abstract
　The changes in the chemical states of co-existing layers of Be and C with vacuum heating were studied for tow different samples using XPS and SIMS surface analysis techniques. One type of sample was a Be plate covered with evaporated C film, denoted as [C/Be], and the other Be implanted with ethylene ions, denoted as [C-Be]. It was found that Be₂C was formed by vacuum heating above 600℃ on the [C/Be] sample. For the [C-Be] sample, however, apart of the surface Be was already changed to Be₂C by the ion implantation. In addition, SIMS measurements showed hydrogen relating secondary ions such as CX^-, C₂X^-, and OX^- (X=H and D), indicating that C and O act as trapping sites of hydrogen isotopes on/in the co-existing layers of Be and C.

松山　政夫^*1、柳原　邦清^*2、山崎　登志成^*2、渡辺　国昭^*1
*1富山大学水素同位体機能研究センター
^*2富山大学工学部電子情報学科 〒930富山市五福3190

Masao MATSUYAMA^*1, Kunikiyo YANAGIHARA^*2, Toshinari YAMAZAKI^*2, and Kuniaki WATANABE^*1
*1Hydrogen Isotope Research Center, Toyama University
^*2Faculty of Engineering, Toyama University
Gofuku 3190, Toyama 930, JAPAN
(Received October 9, 1995; accepted December 22, 1995)

Abstract
　Applicability of the bremsstrahlung counting device to a changeover system of a tritium flow channel has been examined. To simulate a tritium stream, a tritium flow simulator was fabricated. It consists of a radiation detector, low energy X-ray source and its reciprocative motion system. The performance of the tritium flow simulator was examined at first. It was revealed that the simulator could produce preferable peak profiles. In addition, it was observed that the products of a given total count and moving velocity of the X-ray source were almost constant, and also that the simulator performed very well. However, to evaluate the feasibility of an automatic control for the changeover system of a flow channel by a signal from the simulator, the simulator needed to be electrically connected with two valves through a comparator, and the opening and closing action of the two valves have been examined by changing the moving velocity of the radiation source and the accumulation time of the scaler. The preferable action of the two valves could be confirmed, and it was revealed that the bremsstrahlung counting device would be applicable to a changeover system of a tritium flow channel.

舒　衛民、渡辺　国昭

富山大学水素同位体機能研究センター
〒930　富山市五福3190

W. M. SHU and Kuniaki WATANABE
Hydrogen Isotope Research Center, Toyama University,Gofuku 3190, Toyama 930, JAPAN
(Received September 29, 1995; accepted December 22, 1995)

Abstract
　　A general formula for simultaneous plasma- and gas-driven permeation has been developed using the electrical analog approach, in which the permeation potential and resistance are defined for both diffusion in the bulk and recombination on the surface. The formula is used to calculate the permeation flux of deuterium through 316 stainless steel. The theory agreed very well with the experimental results of Doyle and Brice. The dependencies of permeation flux on gas pressure, incident flux, thickness of membrane, ratio of recombination coefficients, ratio of diffusion coefficients and ratio of solubility coefficients on both sides, are also discussed.

原　正憲^*1、小林　孝広^*2、渡辺　国昭^*1、岡部　俊夫^*2､　兜森　俊樹^*3
*1富山大学　水素同位体機能研究センター
^*2富山大学　理学部
〒930　富山市五福3190
^*3日本製綱所(株)　室蘭研究所
〒051　室蘭市茶津町4

Masanori HARA^*1, Takahiro KOBAYASHI^*2, Kuniaki WATANABE^*1, Toshio OKABE^*2, Toshiki KABUTOMORI^*3
*1Hydrogen Isotope Research Center, Toyama University
^*2Faculty of Science, Toyama University
Gofuku 3190, Toyama 930, JAPAN
^*3The Japan Steel Works, Ltd
Chatsu-cho 4, Muroran, Hokkaido 051, JAPAN
(Received October 13, 1995; accepted December 22, 1995)

Abstract
　To understand hydrogen induced disproportionation of ZrCo, the kinetics of disproportionation was studied in the presence of an excess amount of deuterium in a closed system as a function of temperature in the range from 673 to 873K. It was observed that the disproportionation occurred and produced ZrD₂ and ZrCo₂ after the given induction period. The reaction rate became faster the temperature increased up to 773K, but slowed down at higher temperatures. A similar temperature dependence was observed in cyclic heating-cooling experiments. It appears very possible that the hydrogen soluted in ZrCo phase plays an important role regarding disproportionation.

二村　嘉明^*、堀井　一宏^**、河村　弘^{** *}富山大学水素同位体昨日研究センター
〒930　富山市五福3190
^**日本原子力研究所
〒311-11　茨城県東茨城郡大洗町成田町新堀3607

Yoshiaki FATAMURA^*, Kazuhiro HORII^**, Hiroshi KAWAMURA^**
*Hydrogen Isotope Research Center, Toyama University
Gofuku 3190, Toyama 930, JAPAN
^**Japan Atomic Energy Research Institute
3607 Shinbori, Narita, Oarai-machi, Higashi-Ibaraki-gun, Ibaraki-ken, JAPAN

Abstract
　This compilation of data for Li₂O ceramic breeding material is part of a study to construct a database for breeding blanket material for a fusion reactor, consisting of breeding material, neutron multiplier material, construction material, coolant material, purge gas, etc. Data in this compilation are collected from as many papers and reference books as possible.
  Nevertheless, there may be move data taken from past experiments than those collected in this compilation. So authors are going to continue collecting these types of data.
  Data are arranged in a matrix from to clear properties of lack data and to be easily used. This database is expected to be very useful and necessary for designing and analyzing breeding blankets.