日本原子力学会誌
Online ISSN : 2186-5256
Print ISSN : 0004-7120
ISSN-L : 0004-7120
28 巻, 3 号
選択された号の論文の9件中1~9を表示しています
  • 入江 冨士男, 竹尾 正勝
    1986 年 28 巻 3 号 p. 196-202
    発行日: 1986/03/30
    公開日: 2009/07/09
    ジャーナル フリー
    最近,核融合研究に関連して,高磁界超電導マグネットの開発が急速な進展を見せている。大型マグネット製作に適した熱処理後巻線方式による15T台の高磁界マグネットの開発が各所で続けられているが,昨年(1985)九州大学で15.5Tの記録が得られた。しかし,高磁界マグネットにはまだこれに特有な問題点が多く,関連する基礎的研究が要求されている。本稿では,これらの一般的問題点と九大における設計製作の経験およびこれに関連する問題点について述べる。
  • 高橋 義信
    1986 年 28 巻 3 号 p. 203-208
    発行日: 1986/03/30
    公開日: 2009/07/09
    ジャーナル フリー
    軽水炉におけるPu利用(プルサーマル)については欧米諸国では1960年代からすでにその実績があるが,わが国においては1986年に最初のMOX燃料が軽水炉で使用されようとしている。本稿では敦賀1号機におけるMOX燃料照射計画を中心に,プルサーマル利用について概説する。
  • 中川 正祥
    1986 年 28 巻 3 号 p. 209-214
    発行日: 1986/03/30
    公開日: 2009/07/09
    ジャーナル フリー
    核融合装置や加速装置は強磁場を用いた特殊な実験設備であるが,近年では核磁気共鳴診断装置(MRI)の普及によって一般人も強磁場に入る機会が出てきた。本稿では,これまでなされた実験結果の一部を紹介し,磁場に対する生体の反応の仕方およびその強さを示す。また,生体の反応の検出限界値を求めることによって,磁場の安全基準が得られる見込みであること,および現時点での磁場の安全性についての考え方を述べる。
  • 関谷 全, 清瀬 量平
    1986 年 28 巻 3 号 p. 215-221
    発行日: 1986/03/30
    公開日: 2009/07/09
    ジャーナル フリー
    わが国の大学の原子力(核)工学科の多くが25年以上の歴史を持つようになった現在,米国原子力学会(ANS)でも原子力教育の将来を目指し,各国からの招待講演も加えてこれからの25年先を見通しを持って教育のあり方を検討しようとする試みが昨1985年6月のANS年会で行われ,当学会にも働きかけがあった。本稿は,その際の講演内容(米・英・仏・日の4ヵ国から計7件)を要約して解説したものである。
  • 朝倉 健太郎, 藤田 利夫
    1986 年 28 巻 3 号 p. 222-231
    発行日: 1986/03/30
    公開日: 2009/07/09
    ジャーナル フリー
    This paper describes the elevated temperature strength, toughness and alloy design of ferritic steels (dual-phase). For the development of ferritic steels which show excellent characteristics in creep rupture strength, toughness, weldability, resistance to oxidation and corrosion resistance to steam at the service temperature of 550-650°C, extensive studies have been carried out. The effects of Cr, Mo, V, Nb, C and Si on the creep rupture properties and Charpy impact properties of ferritic steels were investigated. The steel obtained from this work, 9Cr-1.5Mo-0.15V-0.05Nb steel, exhibits at least three times as much 105h creep rupture strength at 600°C as compared with 2% Cr-1 Mo steel and conventional 9Cr-IMo steel, and is superior to HT-9 by approximately 50%. This steel also shows higher resistance to embrittlement during service. Moreover, the effect of W on creep rupture properties was investigated, and TB12 steel containing W (12Cr-0.5Mo-1.8 W-0.2V-0.05Nb) was developed. This steel exhibits twice as much 105h creep rupture strength at 650°C as compared with modified 9Cr-1Mo steel and is superior to SUS 316 stainless steel. These new-steels would be useful for boiler tubes, steam generator tubes of fast breeder reactors and first wall of nuclear fusion reactors.
  • 嶋田 純
    1986 年 28 巻 3 号 p. 232-239
    発行日: 1986/03/30
    公開日: 2009/07/09
    ジャーナル フリー
    The high level radioactive waste management is one of the important problems to solve for the public acceptance of the development of nuclear energy. Presently, the geologic disposal has the highest possibility and as for the preliminary step of the research and development of this technique, there exists several research facilities in deep underground formation around the world. Atomic Energy of Canada Ltd. has such underground research facility in undisturbed crystalline bedrock of Canadian shield. This report introduces the outline, development schedule and present situation of this facility.
  • 櫨田 吉造
    1986 年 28 巻 3 号 p. 251-257
    発行日: 1986/03/30
    公開日: 2010/01/08
    ジャーナル フリー
    This report expresses the numerical results of heat transfer phenomena around a high-level radioactive waste repository. The purposes are the mutual influence of ground water flow and heat transfer, and the influence of latent heat for vaporization on the temperature distribution. The 2-dimensional F.E.M. code 'CONVEC' is used for the investigation of the mutual influence of flow and heat, axisymmetric F.E.M. code 'HEAT' is used for the influence of latent heat. The mutual influence is discussed in near and far field. The results of analysis in the near field indicate that heat conduction through rock media is greater than heat transport by water flow. Thus, it is inferred that temperature distribution can be obtained by heat conduction analysis based on Fourier's law. In the far field, the results of analysis indicate that convection flow by radio-genic heat is significant in the case of major fractured rock. Finally, latent heat affects the temperature distribution slightly and desirably. Therefore, the influence of latent heat can be ignored.
  • 複数表面欠陥付直管試験体の疲労試験結果と亀裂伝播評価結果との比較
    柴田 勝之, 横山 憲夫, 大場 敏弘, 川村 隆一, 宮園 昭八郎
    1986 年 28 巻 3 号 p. 258-265
    発行日: 1986/03/30
    公開日: 2009/07/09
    ジャーナル フリー
    It is one of the important subjects to evaluate appropriately the growth of surface cracks to ensure the integrity of a structural component with surface flaws, since the flaws are most frequently detected at the surface of a structural component by non-destructive examinations. Authors have been investigating the growth of surface cracks and the crack growth evaluation method, in which interaction and surface effect in multiple crack growth are considered, was proposed previously using empirical expressions.
    In the meanwhile, verification tests using structural component models were performed to confirm the validity of the evaluation method. In this paper is described the growth behavior of multiple surface cracks obtained from fatigue tests of straight pipes with multiple surface cracks in the inner surface, and is discussed the applicability of the growth evaluation method proposed in this study and that specified by the ASME Code Sec. E. Reasonable fatigue behavior evaluations were obtained by the proposed method for the straight pipes, whereas the method of the ASME Code Sec. XI gave overly conservative fatigue lives.
  • 山崎 仲道, 柳沢 和道, 西岡 守
    1986 年 28 巻 3 号 p. 266-273
    発行日: 1986/03/30
    公開日: 2010/01/08
    ジャーナル フリー
    The lithification of borosilicate glass powder containing simulated high level radioactive waste with the hot pressing technique under hydrothermal conditions was investigated. The glass powder was easily formed to hardened body with a little distilled water (5-10w/0). This glass body showed a high compressive strength above 2, 500 kg/cm2. The lithification occur-red at 240-270°C with the rapid shrinkage. The initial shrinkage kinetics were examined in consideration of the dissolution core model: 1-(1-x)1/3=kt1/2, 1-(1-x)1/3=k't, where x is the shrinkage ratio, k and k' the constants and t the reaction time. The apparent activation energy of shrinkage below 250°C was found to be about 20 kcal/mol, which was good agreement with that of the growth of surface reaction layer in hydrothermal solution. It was suggested that the initial stage of lithification followed the dissolution-deposition model.
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