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30 巻, 11 号
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中川 弘1988 年 30 巻 11 号 p. 962-970
発行日: 1988/11/30
公開日: 2009/03/31
ジャーナル フリー「常陽」,「もんじゅ」の成果をうけて, FBR実証炉を着工しようという気運が高まる中で,実証炉に関する本格的研究開発が始められようとしている。原子力委員会の「長期計画」に沿いつつ,実際の活動では動燃,原電,原研,電中研等の関係機関で調整しながら進められているFBR実証炉開発の現状を,技術的な面から解説する。1990年頃に基本仕様の選定, 1990年代後半に着工を目指して,将来はLWRなみの経済性を達成しようとする意図に沿った概念設計研究や,設計主要目の研究のねらいと諸課題,それらを解明する研究開発の主要題目等を筋立てて概説する。FBR実証炉の開発は,従来の研究開発の単なる延長にはなく.難しい課題の克服が必要と考えられ,そのための研究が続けられている。抄録全体を表示PDF形式でダウンロード (863K) -
宮尾 英彦, 間野 正, 池田 諭志, 塩月 正雄, 菅谷 敏克1988 年 30 巻 11 号 p. 971-978
発行日: 1988/11/30
公開日: 2009/03/31
ジャーナル フリー放射性物質の分布および量を遠隔,自動にて測定して映像化する手法として,動燃事業団では放射線映像化装置を開発している。本稿では,試作(プロト) 1号機の概要と評価試験結果および今後の計画を解説する。抄録全体を表示PDF形式でダウンロード (12665K) -
土橋 敬一郎, 林 正俊, 岩崎 智彦1988 年 30 巻 11 号 p. 979-985
発行日: 1988/11/30
公開日: 2009/03/31
ジャーナル フリーThe ANS (Advanced Neutron Source) project being planned by Oak Ridge National Laboratory (ORNL) under the control of U.S. DOE will provide an unprecedented high flux reactor for the study of neutron scattering. This reactor will also provide isotope production and material irradiation facilities that are as good as, or better than HFIR (High Flux Isotope Reactor). The Japan is hoped to join the project. This note introduces the current status of the project by describing the '88 reference core design and discusses the R&D items.抄録全体を表示PDF形式でダウンロード (548K) -
V. A. LEGASOV, V. M. NOVIKOV, 古川 和男, 田井 正博1988 年 30 巻 11 号 p. 986-992
発行日: 1988/11/30
公開日: 2009/03/31
ジャーナル フリーExperience of nuclear power plants (NPP) operation has demonstrated that the nuclear safety concepts which has been dominating hitherto are too optimistic. Safety and economic efficiency are becoming “weak points” impeding extensive development of the nuclear power (NP). Since accidents in NP may have international consequences the safety requirements must be formulated proceeding from the expected scale of the world nuclear power development. The analysis of the typical scenarios shows that in NP development two stages may be outlined.
The basis of the first one (up to the years 2000) is recent generation of reactors for which the increasing safety program is being realized.
The second stage will require development and introduction the next generation of a safer reactor.
In the present paper the physical causes determining the possibility of high hypothetical accidents with severe consequences and the ways of their blocking or elimination have been considered. This makes it possible to formulate some criteria of the concept of the next generation safer reactor. Development of the concept assumes some clearly ontlined stages. The necessity for extension of a reachable safety level of the next generation reactor for all elements of the external nuclear fuel cycle is emphasized.抄録全体を表示PDF形式でダウンロード (577K) -
井門 俊治, 辻 龍介1988 年 30 巻 11 号 p. 999-1001
発行日: 1988/11/30
公開日: 2009/03/31
ジャーナル フリーPDF形式でダウンロード (213K) -
プレナムブロック内の7噴流混合実験功刀 資彰1988 年 30 巻 11 号 p. 1002-1004
発行日: 1988/11/30
公開日: 2009/03/31
ジャーナル フリーPDF形式でダウンロード (193K) -
立石 嘉徳, 柚原 俊一, 柴原 格, 伊藤 正彦, 野村 茂雄, 佐藤 義則, 吉田 英一, 鹿倉 栄1988 年 30 巻 11 号 p. 1005-1019
発行日: 1988/11/30
公開日: 2009/03/31
ジャーナル フリーA modified SUS 316 stainless steel (PNC 316) for high burnup fast reactor core application has been successfully developed. The material 16Cr-14Ni-2.5Mo-0.25P-0.004B-0.1Ti-0.1Nb steel is utilized with 20% cold-worked condition. The steel exhibits excellent characteristics in creep rupture strength and swelling resistance, and is superior to any other Type 316 class stainless steels, i.e. 104 h creep rupture strength greater than 200 MPa at 650°C and swelling less than 1% at neutron fluence of 1.9×1023n/cm2 (E>0.1 MeV).
Reliability of this steel has been confirmed by fast reactor irradiation of 26, 000 fuel elements and 500 fuel sub-assemblies. Postirradiation examination of the fuel elements revealed the excellent characteristics in dimensional stability, compatibility with sodium as well as fission products and radiation induced mechanical property changes, compatible with a current high burnup design target.
Specifications and techniques have also been developed for the inspection of large amount of claddings, wrapper tubes and other parts for fuel sub-assemblies.抄録全体を表示PDF形式でダウンロード (9194K) -
JPDR強制循環系における実証試験諏訪 武, 後藤 覚司, 五来 健夫, 栗林 伸英, 根本 吉則, 星 三千男, 佐川 千明, 米沢 仲四郎, 中原 勇, 宮崎 一郎, 安 ...1988 年 30 巻 11 号 p. 1020-1029
発行日: 1988/11/30
公開日: 2009/03/31
ジャーナル フリーThe new decontamination process using sulfuric acid-cerium (IV) solution (SC process) for reactor dismantling has been developed and demonstrated to evaluate its applicability at the recirculation system of the JPDR (A-loop). The decontamination test loop with the surface area of 42.7 m2 (contaminated area of 9.2 m2) and solution volume of ca. 2.3 m3 consisted of the main circulation, Ce4+-regeneration and waste solution treatment lines. The decontaminationstep was operated with continuous electrolytic regeneration of Ce4+ from Ce3+ to maintain the Ce4+ concentration in the range of 12×10-3 M at Ce4+/Ce3+≤0.1.
The test results are summarized as followed: (1) The decontamination factors (DF) for sampling specimens after the decontamination were ranged 3601, 800. (2) The corrosion rate of the test loop increased linearly with a flow rate (0.552.6 m/s) in the presence of Ce4+. (3) Burst of scale (similar to cruds) in the early stage of the decontamination led to the decrease of Ce4+ concentration. (4) The desired values to be a current efficiency ηe≥80% at 50A/m2 was obtained in the electrolytic regenerating cell.
The results of demonstration test on the SC process indicate that a high decontamination factor can be obtained in a low Ce4+ concentration by means of its electrolytic regeneration.抄録全体を表示PDF形式でダウンロード (729K) -
笠原 孝保, 西沢 靖雄, 加藤 監治1988 年 30 巻 11 号 p. 1030-1037
発行日: 1988/11/30
公開日: 2009/03/31
ジャーナル フリーA method, based on AI techniques, has been developed for detecting and removing interferences among maintenance tasks in nuclear power plants. This method helps plant operators by adjusting the time schedule of the various tasks so that incorrect ordering or timing of plant manipulations does not cause undesirable results, such as a plant trip. This method consists of three main parts.
(1) Checking for interference among tasks and plant conditions by analyzing effects of manipulating one component on other components.
(2) Searching for a method to remove interference by isolating the problem component from the others.
(3) Adding new operations and readjusting the time schedule by the branch and bound method.
The performance of this method was checked by off-line simulation test. The result showed that the method can examine and remove the interferences among maintenance tasks.抄録全体を表示PDF形式でダウンロード (605K) -
平尾 桂一, 山根 寿己, 南埜 宜俊, 田中 昭衛1988 年 30 巻 11 号 p. 1038-1044
発行日: 1988/11/30
公開日: 2009/03/31
ジャーナル フリーEffects of applied stress on failure time in stress corrosion cracking of Zircaloy-4 alloy were investigated by Weibull distribution method. Test pieces in the evaculated silica tubes were annealed at 1, 073 K for 7.2×103s, and then quenched into ice-water. These species under constant applied stresses of 4090% of yield stress were immersed in CH3OH-1 _??_ I2 solution at room temperature.
The probability distribution of failure times under applied stress of 40% of yield stress was described as single Weibull distribution, which had one shape parameter. The probability distributions of failure times under applied stress above 60% of yield stress were described as composite and mixed Weibull distributions, which had the two shape parameters of Weibull distributions for the regions of the shorter time and longer one of failure. The values of these shape parameters in this study were larger than the value of 1 which corresponded to that of wear out failure. The observation of fracture surfaces and the stress dependence of the shape parameters indicated that the shape parameters both for the times of failure under 40% of yield stress and for the longer ones above 60% of yield stress corresponded to intergranular cracking, and that for shorter times of failure corresponded to transgranular cracking and dimple fracture.抄録全体を表示PDF形式でダウンロード (2647K) -
1988 年 30 巻 11 号 p. 1046
発行日: 1988/11/30
公開日: 2009/03/31
ジャーナル フリーPDF形式でダウンロード (133K)
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