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38 巻, 2 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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富永 健, Montague COHEN1996 年 38 巻 2 号 p. 85-97
発行日: 1996/02/29
公開日: 2009/04/21
ジャーナル フリーPDF形式でダウンロード (24259K) -
安田 徳一1996 年 38 巻 2 号 p. 98-105
発行日: 1996/02/29
公開日: 2009/04/21
ジャーナル フリー電離放射線に被ばくして生ずる影響は,被ばく線量と影響の現れ方との関係で,確率的影響と確定的影響とに分けることができる。また観点を変えると,影響が被ばくした当人に現れる身体的影響と子孫に現れる遺伝的影響とに区別することもできる。
動物実験では電離放射線に被ばくして遺伝的影響の生ずることは明らかである。一方,電離放射線被ばくについて最大の集団である原爆被爆者から遺伝的影響の確認された子孫は検出されていない。これはどのように解釈すべきか。そもそもヒトで放射線被ばくによる遺伝的影響を検出することができるのであろうか。この問題を平易に解説する。抄録全体を表示PDF形式でダウンロード (3391K) -
「システム安全工学実験設備」研究専門委員会藤家 洋一1996 年 38 巻 2 号 p. 106-114
発行日: 1996/02/29
公開日: 2009/04/21
ジャーナル フリーThe Research Committee on Experimental Facilities for Nuclear Systems Safety was established in the Atomic Energy Society of Japan at April, 1993. A total of 10 meetings has been held in the last two years to discuss future prospects on the experimental facilities for nuclear systems safety. The discussions during these meetings extend from safety logic for future nuclear facilities to the experimental facilities for the safety enhancement of the light water reactors, fast reactors, high temperature gas cooled reactors and fuel cycle facilities including waste treatment and disposal. In the meantime a questionnaire on the safety requirements for future nuclear facilities and related research needs was sent out to the member of the Committee and the results were summarized. These are summarized in this report.抄録全体を表示PDF形式でダウンロード (3690K) -
和嶋 常隆, 川島 克之, 山下 隆1996 年 38 巻 2 号 p. 133-142
発行日: 1996/02/29
公開日: 2009/04/21
ジャーナル フリーA study is made on a strategy analysis of the long term nuclear fuel cycle systems deployment in accordance with the nuclear power growth projection and fast breeder reactor (FBR) introduction. In the analysis, thereprocessed plutonium (Pu) is charged into the reactor in such a way that the reprocessed Pu is not stored outside the reactor, i.e., there is no excess Pu outside the reactor. The analysis characterized the fuel cycle systems, and showed the usefulness of the present method to determine future directions for the FBR introduction and nuclear fuel cycle systems deployment. Concerning an intermediate-term strategy, the time of introduction and required capacities of a second commercial LWR reprocessing plant, Pu-thermal, and the first FBR reprocessing plant deployment are evaluated. A long term strategy analysis shows that the two or three large plants are run in parallel for each fuel cycle facility and that FBR related facilities deal with a markedly large amount of Pu. It is concluded that the early stage introduction of FBRs of significant capacities seems necessary to materialize a consistent total FBR/fuel cycle system where Pu balance becomes feasible through its flexible operation of, for instance, adjusting breeding ratio, in order to keep the transparency of the Pu utilization.抄録全体を表示PDF形式でダウンロード (4423K) -
鎌田 耕治, 木下 博嗣, 高橋 平七郎, 垣花 秀武1996 年 38 巻 2 号 p. 143-153
発行日: 1996/02/29
公開日: 2010/03/08
ジャーナル フリーAnomalous heat evolution was observed in deuteron-implanted Al foils upon 175keV Electron bombardment. Local regions with linear dimension of more than 100nm each showed simultaneous transformation from single crystalline to polycrystalline structure in roughly one minutes on the electron bombardment, indicating the temperature rise up to more than melting point of Al from room temperature. The amount of energy necessary for the transformation was typically 160MeV for each transformed region. The transformation was never observed in proton-implanted Al foils.
Microstructures in the subsurface layer of the implanted Al, investigated by the collaboration of ERD and TEM, were presented for numerical discussions of the experimental results.
Possible causes of the surface melting, such as heating effect of the electron beam, size effect of the melting point, difference of the implanted depth profiles between the hydrogen and deuterium, and possible chemical reactions due to the electron bombardment in D2 collections were investigated, and the conclusion is inevitable that some kind of nuclear reactions which takes place in the D2 collections is responsible for the melting. The reaction was estimated to continue for a short time, presumably less than 10-10, and the energy gain, which is defined as the ratio between the amount of energy evolved and the energy loss of the impinging electrons through the Al specimen, amounts to more than 1×105.抄録全体を表示PDF形式でダウンロード (13383K) -
炉心の黒鉛流路管温度が非均一の場合武田 哲明, 武仲 五月, 菱田 誠1996 年 38 巻 2 号 p. 154-162
発行日: 1996/02/29
公開日: 2009/04/21
ジャーナル フリーA primary pipe rupture accident is one of the design-basis accidents of a High-Temperature Gas Cooled Reactor (HTGR). When the primary pipe rupture accident occurs, air is expected to enter the reactor core from the breach and oxidize in-core graphite structures. During the accident a complicated multi-component gas flow is expected to occur in the reactor vessel. This paper deals with experimental study on the process of air ingress into an apparatus simulating the HTGR during the 1st stage of the accident. Present study focuses on investigating the density change of the gas mixture, concentration change of each gas species, and duration of the 1st stage of the accident when the temperature of the central flow path is higher than that of the peripheral ones and when the temperature of the reactor simulator decreases with time after the pipe rupture accident. It was found that the cooling rate of the reactor core temperature for preventing natural circulation of air existed. The results of the density and concentration changes in the non-uniform temperature case are almost the same as those in the uniform temperature case if natural circulation does not occur in the reactor core flow paths.抄録全体を表示PDF形式でダウンロード (3396K)
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