巻号一覧
後続誌
28 巻, 12 号
選択された号の論文の6件中1～6を表示しています
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近藤 駿介, 松岡 猛, 飯田 式彦, 早田 邦久, 阿部 清治, 飛岡 利明, 小林 健介, 村上 秀明, 可児 吉男, 中村 隆夫1986 年 28 巻 12 号 p. 1096-1128
発行日: 1986/12/30
公開日: 2010/01/08
ジャーナル フリーPDF形式でダウンロード (2079K) -
荒 邦章, 大山 信美1986 年 28 巻 12 号 p. 1129-1134
発行日: 1986/12/30
公開日: 2009/07/09
ジャーナル フリー高速増殖炉(FBR)では,冷却材に液体金属Naを使用するため,計測器類は軽水炉とは異なった種々の特徴あるものが見られる。本稿では,FBRに固有の環境,すなわち高温雰囲気,光学的に不透明なNa等の条件下における試験,検査等を目的とした計測技術に関して,研究開発の現状と動向を解説する。抄録全体を表示PDF形式でダウンロード (8382K) -
1986 年 28 巻 12 号 p. 1134
発行日: 1986年
公開日: 2009/07/09
ジャーナル フリーPDF形式でダウンロード (1954K) -
核・熱特性および事故再現性解析若林 利男, 望月 弘保, 緑川 浩掌, 速水 義孝, 北原 種道1986 年 28 巻 12 号 p. 1153-1164
発行日: 1986/12/30
公開日: 2010/01/08
ジャーナル フリーThe accident at the 4th unit of Chernobyl Nuclear Power Station was analyzed by using an integrated analysis codes system developed for the design of Advanced Thermal Reactor (ATR) in Japan, a heavy water moderated pressure tube type reactor. The computer programs, and analytical models in the codes system have been verified by experiment analyses carried out at O-arai Engineering Center and "FUGEN" power plant of Power Reactor and Nuclear Fuel Develop-ment Corp., a demonstration plant of ATR. The calculation condition for the resented Chernobyl accident were based on plant specifications and operating history of the Chernobyl power station described in the accident report and some references published hydraulic characteristics of the Chernobyl reactor were calculated, and used as input condition to the subsequent calculations of the plant behavior on the sequence of events during the accident.
The analytical results agreed well with the data designed in the official report by Soviet Union with respect to the reactivity coefficients and over all plant behavior during the transient.抄録全体を表示PDF形式でダウンロード (4095K) -
浜田 省三1986 年 28 巻 12 号 p. 1165-1171
発行日: 1986/12/30
公開日: 2009/07/09
ジャーナル フリーTransmission electron microscopy (TEM) is applied to the direct observation of the depth dependent damage structure in ion-irradiated stainless steel by using the cross-section technique; obtaining the TEM specimen from a slice of the irradiated stainless steel with thick Ni plating. Here has been developed the specimen preparation method of cross-section technique without heat treatment, which was necessary in the conventional method to strengthen the bonding between Ni and stainless steel. Nickel plating with good bonding to stainless steel is enabled by the following manner.
First, the irradiated stainless steel is immersed in the Wood's nickel solution at room temperature for 60 s to activate the surface, followed by the stricking for 300s at a current density of 300 Aim' in the solution to make fine and homogeneous nucleation of Ni on the stainless steel. Then, the sample is plated with Ni in the Watt's nickel plating solution at 333 K with current density of 900∼1, 000 A/m2. The TEM disc is obtained by mechanical slicing from the specimen with Ni plating of more than 3 mm thickness. Electropolishing is accomplished by using both Ballmann method and jet electropolishing to perforate the disc accurately at the aimed point for the observation of the damage structure.抄録全体を表示PDF形式でダウンロード (12648K) -
佐藤 千之助, 淡路 英夫, 川又 清弘, 車田 亮, 奥 達雄1986 年 28 巻 12 号 p. 1172-1179
発行日: 1986/12/30
公開日: 2009/07/09
ジャーナル フリーNew fracture criteria of graphite under multi-axial stress state are presented for the design of the core and the support materials of the high-temperature gas-cooled reactor(HTGR). Different kinds of fracture strength tests are carried out for IG-11 graphite as a candidate material for the HTGR. From these results, the fracture criteria are verified by the fracture mechanics approach. Then the minimum ultimate strengths corresponding to the survival probability 99% in the confidence level 95% showing the allowable stress values in the safety design are presented. These values are also shown on the bi-axial stress diagram.抄録全体を表示PDF形式でダウンロード (3878K)
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