巻号一覧
後続誌
18 巻, 11 号
選択された号の論文の9件中1～9を表示しています
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瑞慶覧 篤, 井上 晃次, 鈴木 威男, 川島 協1976 年 18 巻 11 号 p. 672-684
発行日: 1976/11/30
公開日: 2009/03/31
ジャーナル フリー高速増殖原型炉「もんじゅ」のために実施された模擬臨界実験,その解析ならびに炉心設計への反映について概要を解説する。抄録全体を表示PDF形式でダウンロード (2710K) -
佐藤 章一1976 年 18 巻 11 号 p. 685-690
発行日: 1976/11/30
公開日: 2009/03/31
ジャーナル フリー原子力を広い利用分野をもつ水素の燃焼熱(水素エネルギー)に変換することにより,水素をエネルギー担体とする水素エネルギー・システムの成立が期待される。このような非電力利用に適した原子炉は高温ガス炉であるが,水素製造プロセスなどへの応用には,炉とプロセスの境界に関する検討と,核熱を有効利用できる経済的なプロセスの確立が必要である。抄録全体を表示PDF形式でダウンロード (546K) -
森山 昇1976 年 18 巻 11 号 p. 691-695
発行日: 1976/11/30
公開日: 2009/03/31
ジャーナル フリー原子力の利用とともに放射性廃棄物の処理処分が重要な問題となっている。アスファルト固化は放射性廃棄物の処理に有望な方法として広く採用されているが,その処分を考えた場合必ずしも安全であるとはいい切れない。本稿では,陸地保管,地中処分,海洋処分を対象としそれぞれの処分に要求される物性を挙げ,アスファルト固化体が処分体としてどの程度これらの要求を満たしているか,またどういう問題点があるかについて論ずる。抄録全体を表示PDF形式でダウンロード (433K) -
石川 晃司1976 年 18 巻 11 号 p. 696-700
発行日: 1976/11/30
公開日: 2009/03/31
ジャーナル フリーInservice Inspection (ISI) for the nuclear power plants is steadily progressing in Japan.
Philosophy and technology of ISI has been introduced from the U.S.A. In application of ISI to the plants in Japan, potential problems have been revealed as experienced, for example, discrepancies between the engineering requirements for component manufacturing and ISI, slow progress of development of ISI equipment and so on.
The problems of codes and regulations such as Section XI of ASME Code are discussed in relation with the actual application in Japan.抄録全体を表示PDF形式でダウンロード (2739K) -
斯波 正誼, 竹下 功1976 年 18 巻 11 号 p. 701-709
発行日: 1976/11/30
公開日: 2009/03/31
ジャーナル フリーThe LOFT Program is an integral experiment to evaluate performance of PWR ECCS under LOCA conditions with its facility-the extensively instrumented 55 MW PWR facility-designed for LOCA experiments. The LOFT facility consists of 1 1/2 primary coolant loop, nuclear core, reactor vessel and adaptable ECCS.
In 1976, the Japan Atomic Energy Research Institute participated in the program with the term going over 4 years. The purpose is to help asses and improve the PWR LOCA/ECCS analytical methods (PWR LOCA/ECCS models) being developed in JAERI.
Thermal and hydraulic behavior of the PWR as a total system during hypothetical LOCA can be calculated by the LOCA/ECCS models, which are composed of basic, small models of the respective components and LOCA events. Verification of the LOCA/ECCS models is possible by comparing the LOFT experiments with the input/output informations transferred among the sub-models.抄録全体を表示PDF形式でダウンロード (4646K) -
武田 宏, 山本 寛1976 年 18 巻 11 号 p. 716-721
発行日: 1976/11/30
公開日: 2009/03/31
ジャーナル フリーTemperature distribution in spouted bed was measured by using brass and graphite spouted beds so as to investigate heat transfer characteristic of spouted bed applied to an apparatus of PyC coating.
These spouted beds are batch type and are spouted by air or nitrogen gas of room temperature, and the outer wall of beds are heated by nichrome or graphite heater. Particles used for experiments are alumina spherical particles and the diameter is 0.80-1.12 mms∅. Temperature condition is in the range of 400-1, 400°C.
In the neighborhood of 400°C, the spouting condition is stable, while the spouting condition becomes unstable in the case of above 1, 000°C. This is caused by abrupt temperature increase of spouting gas.
It was found that heat transfer coefficient hw of our low temperature experiments was closer to the calculated from Malek et al.'s equation, hp of our experiments was several times greater than the calculated from Uemaki et al.'s equation. On the other hand, hp of high temperature experiments was compared with an experimenta relation for convective heat transfer of fluidized bed, it was found that Nup of our experiments was nearly equal to or greater than the calculated from the relation, this would be caused by radiant heat transfer.抄録全体を表示PDF形式でダウンロード (2315K) -
高濃縮ウラン使用転換炉の活用と高温ガス冷却炉との共存性古橋 晃1976 年 18 巻 11 号 p. 722-730
発行日: 1976/11/30
公開日: 2009/03/31
ジャーナル フリーSaving of material requirements in the long-term fuel cycle is studied by introducing molten-salt reactors with good neutron economy into a projection of nuclear generating capacity in Japan. In this second report utilization of molten-salt converter reactors using highly enriched uranium as forerunners of molten-salt breeder reactors is examined.
It is shown that the saving effect on the cumulative demand for natural uranium will be fairly large if the repartition of generating capacity among reactor types is suitably planned. Coexistence of high temperature gas cooled reactors with molten-salt breeder reactors is also planned. The former plays the role of 233U producer for the latter and, in later periods, the latter produces excess fuel which enables the introduction of the high temperature gas cooled reactors for nuclear heat utilization.抄録全体を表示PDF形式でダウンロード (677K) -
「欧文誌」投稿者のために吉田 正男1976 年 18 巻 11 号 p. 731-732
発行日: 1976/11/30
公開日: 2009/03/31
ジャーナル フリーPDF形式でダウンロード (186K) -
1976 年 18 巻 11 号 p. 733-734
発行日: 1976/11/30
公開日: 2009/03/31
ジャーナル フリーPDF形式でダウンロード (245K)
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