巻号一覧
後続誌
21 巻, 12 号
選択された号の論文の7件中1～7を表示しています
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高橋 亮人1979 年 21 巻 12 号 p. 903-909
発行日: 1979/12/30
公開日: 2009/04/21
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松井 隆1979 年 21 巻 12 号 p. 910-915
発行日: 1979/12/30
公開日: 2009/04/21
ジャーナル フリーFor more than a decade, physics study as fundamental research in fusion nuclear has progressed with great strides and the fruit therefrom has been rather worldwdely exchanged among the concerned scientists of each fusion developing powers.
In recent years, fusion research and development is entering into the stage of engineering feasibility study, and the four great powers in fusion, USA, USSR, Euratom and Japan, are now independently manufacturing large fusion experimenting devices. On the other hand, international cooperation having some institutional structure has become considered meritful and necessary from the viewpoints of cost and efficiency of research and development.
International Energy Agency (IEA) and International Atomic Energy Agency (IAEA) are managing various kinds of conference and projects in order to generate cooperation in this field. Fusion Power Coordinating Committee (FPCC), under IEA, hosts LCT project and TEXTOR project. IAEA is promoting INTOR project. There are also many kinds of bilateral cooperation under practice, such as Japan-US, Japan-USSR etc. As the research and development on fusion progresses further and further, the more activated and accelerated the international cooperation in this field will become.抄録全体を表示PDF形式でダウンロード (536K) -
原研・東海研究所および大洗研究所松本 徳太郎, 坂倉 敦, 大内 正博, 石本 清1979 年 21 巻 12 号 p. 916-924
発行日: 1979/12/30
公開日: 2009/04/21
ジャーナル フリーThree hot laboratories have been in operation for post-irradiation examination of fuel and material specimens at the Tokai Research Establishment and the Oarai Research Establishment of Japan Atomic Energy Research Institute. Tokai Hot Laboratory is mainly used for post-irradiation examinations of particle fuels, VHTR materials, fusion reactor materials and gas cooled power reactor fuel. JMTR Hot Laboratory, adjacent to the JMTR reactor building, is employed for a variety of work, such as capsule dismantling, fuel and material examination of specimens irradiated at JMTR. Reactor Fuel Examination Facility is located at Tokai, and is well qualified and equipped to perform post-irradiation examinations of power reactor fuels for safety evaluation.抄録全体を表示PDF形式でダウンロード (4640K) -
八巻 治恵, 堀木 欧一郎, 一色 正彦1979 年 21 巻 12 号 p. 925-934
発行日: 1979/12/30
公開日: 2009/04/21
ジャーナル フリーThe actual status of JRR-2 and JMTR is reported, as fuel and material irradiation facilities. The present report introduces; the general descriptions of the reactors and operating histories; the in-core irradiation facilities and some techniques connected with fuel and material irradiation such as temperature measurement and control.抄録全体を表示PDF形式でダウンロード (3086K) -
北川 一男1979 年 21 巻 12 号 p. 935-939
発行日: 1979/12/30
公開日: 2009/04/21
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モニタリング項目の選定手法井上 頼輝, 森澤 眞輔1979 年 21 巻 12 号 p. 948-956
発行日: 1979/12/30
公開日: 2010/03/08
ジャーナル フリーA selection method of monitoring items in an environmental monitoring around a radioactive waste burial site was discussed by comparing the superiority of each monitoring item. Higher superiority was given to the monitoring item of which measurement error would lead to smaller estimation error of an internal radiation dose to man, supposing that the evaluation of the internal radiation dose to man was valid.
Two practicable monitoring items (radionuclide concentrations in groundwater and those in soil) which are on the same transportation pathway of radionuclides to man, and those (radionuclide concentrations in drinking water and those in irrigation water; concentrations in drinking water and those in soil) which are on different transportation pathways, were picked up and those superiorities were evaluated supposing that 90Sr would mainly contribute to the radiological hazards to man which would be caused by the radioactive wastes disposed in the ground. The effect of background concentration of 90Sr on a selection of monitoring items was not discussed.抄録全体を表示PDF形式でダウンロード (2277K) -
佐藤 千之助, 今村 好男, 川又 清弘, 淡路 英夫, 奥 達雄1979 年 21 巻 12 号 p. 957-967
発行日: 1979/12/30
公開日: 2009/04/21
ジャーナル フリーThis paper describes changes in the thermal shock resistance Δ=σtk/Eα(σt: tensile strength, k: thermal conductivity, E: Young's modulus, α: coefficient of thermal expansion) and the thermal shock fracture toughness ∇=KIck/Eα(KIc: fracture toughness value of the mode I) in addition to usual mechanical properties including the diametral compressive strength and fracture toughness of four varieties of graphite (IM2-24, 7477, H327 and SMG) for the high temperature gas-cooled reactor due to neutron irradiations of (1.6-2.3)×1021n/cm2(>0.18MeV) at 600-850°C. These experimeats are carried out by means of our recently developed techniques using small disk type specimens which are very effective for a capsule irradiation in the JMTR. Both the thermal shock resistance and the thermal shock fracture toughness of graphites after irradiation are expressed to decrease remarkably in contrast with the increase of the usual mechanical strength.抄録全体を表示PDF形式でダウンロード (12845K)
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