著者

黒澤 龍平

出版者

一般社団法人 日本原子力学会

雑誌

日本原子力学会誌 (ISSN:00047120)

巻号頁・発行日

vol.17, no.9, pp.477-482, 1975-09-30 (Released:2010-04-19)

参考文献数

24

著者

須山 一兵 江藤 久美

出版者

一般社団法人 日本原子力学会

雑誌

日本原子力学会誌 (ISSN:00047120)

巻号頁・発行日

vol.23, no.8, pp.564-570, 1981

被引用文献数

1

著者

山口 武雄

出版者

一般社団法人 日本原子力学会

雑誌

日本原子力学会誌 (ISSN:00047120)

巻号頁・発行日

vol.25, no.11, pp.895-900, 1983

著者

井上 晃 高橋 実

出版者

一般社団法人 日本原子力学会

雑誌

日本原子力学会誌 (ISSN:00047120)

巻号頁・発行日

vol.30, no.9, pp.821-837, 1988-09-30 (Released:2009-03-31)

著者

伊藤 早苗 伊藤 公孝

出版者

一般社団法人 日本原子力学会

雑誌

日本原子力学会誌 (ISSN:00047120)

巻号頁・発行日

vol.34, no.6, pp.500-505, 1992

著者

山路 昭雄 沼田 茂生 斉藤 鉄夫

出版者

一般社団法人 日本原子力学会

雑誌

日本原子力学会誌 (ISSN:00047120)

巻号頁・発行日

vol.29, no.6, pp.555-563, 1987

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A design method is described for the Fe compensational shield which is located around a straight duct in concrete shield wall against γ radiation to compensate the lowering of shielding efficiency caused by the duct. The method has been applied to the configuration, where the source area is not viewed through the duct from the detector point at the duct exit. The form of the compensational shield was determined depending on the wall thickness, the duct diameter, the incident angle of γ-ray beam to the wall, and the densities of the concrete and Fe. An experiment for the compensational shield was performed in the Dry Shielding Facility at JRR-4. The measured dose rates behind the wall were reduced effectively by the compensational shield, so that the maximum dose rates became only slightly higher than that of the bulk shield wall and the dose rates higher than the maximum dose rate for bulk shield wall were restricted only in the area near the duct exit. The experimental results have been analyzed using a multigroup γ-ray single scattering code G33YSN.

著者

鬼柳 善明 田中 知 今西 信嗣 竹田 敏一 工藤 和彦

出版者

一般社団法人 日本原子力学会

雑誌

日本原子力学会誌 (ISSN:00047120)

巻号頁・発行日

vol.42, no.9, pp.851-867, 2000-09-30 (Released:2009-04-21)

著者

吉川 允二 三好 昭一 中井 貞雄 井上 信幸 松田 慎三郎 永島 孝 宮 健三 関昌 弘 井上 晃 石野 栞 伊尾木 公裕 小澤 由行

出版者

一般社団法人 日本原子力学会

雑誌

日本原子力学会誌 (ISSN:00047120)

巻号頁・発行日

vol.31, no.1, pp.104-127, 1989-01-30 (Released:2009-04-21)

著者

松下 正 佐々木 茂雄

出版者

一般社団法人 日本原子力学会

雑誌

日本原子力学会誌 (ISSN:00047120)

巻号頁・発行日

vol.22, no.1, pp.17-22, 1980-01-30 (Released:2009-03-31)

参考文献数

2

被引用文献数

1 1

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1979年3月に本格運転を開始した新型転換炉原型炉「ふげん」発電所は,わが国で初めての重水減速軽水沸騰冷却型原子炉である。減速材系,すなわち重水系より発生する劣化重水を再使用するために重水濃縮を行う重水精製装置を設置した。重水精製装置は,建屋工事を含めると1977年12月より建設に着手し, 79年4月末に良好な結果をもって完成することができた。装置は無隔膜減容電気分解方式を採用し,年間95W/Oの劣化重水5tを濃縮し, 99.8W/Oの重水を4.4t回収する設備能力を有する。本稿では,装置の設計,建設,運転結果について述べる。

著者

伊藤 早苗 伊藤 公孝

出版者

一般社団法人 日本原子力学会

雑誌

日本原子力学会誌 (ISSN:00047120)

巻号頁・発行日

vol.34, no.6, pp.500-505, 1992-06-30 (Released:2010-04-19)

参考文献数

15

著者

田下 昌紀

出版者

一般社団法人 日本原子力学会

雑誌

日本原子力学会誌 (ISSN:00047120)

巻号頁・発行日

vol.12, no.3, pp.135-144, 1970-03-30 (Released:2011-02-17)

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On October 5, 1966, during a slow increase in power, the Enrico Fermi Reactor was shut down in an orderly manner after it was obseryed that the control rods were withdrawn further than normal for 31MWt, that several subassemblies had abnormally high outlet temperatures, and that a small amount of F.P. was detected by the F.P. detector.Subsequently various investigations and analyses were performed to elucidate and to assess this incident. It was established as a result that fuel melting had occurred in two fuel subassemblies, M-098 and M-127.Inspection of the lower plenum and study of the analytical model indicated that one of the two Zr segments originally installed on the conical flow guide had become loose and had partially blocked the inlet nozzles of four subassemblies adjacent to each other. To prevent recurrence of similar trouble, the remaining Zr segments on the conical flow guide were removed, and a malfunction detection analyzer was installed in the instrumentation and safety system.Preoperational tests are now under way, with the Enrico Fermi Atomic Power Plant scheduled to be restored to full power operation in February 1970.This report outlines the fuel melting incident and the subsequent repairs and modifications brought upon the reactor.

著者

山路 昭雄 宮越 淳一 岩男 義明 壺阪 晃 斉藤 鉄夫 藤井 孝良 奥村 芳弘 鈴置 善郎 河北 孝司

出版者

一般社団法人 日本原子力学会

雑誌

日本原子力学会誌 (ISSN:00047120)

巻号頁・発行日

vol.26, no.2, pp.139-156, 1984

被引用文献数

2

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Procedures of shielding analysis are described which were used for the shielding modification design of the Nuclear Ship "MUTSU". The calculations of the radiation distribution on board were made using Sn codes ANISN and TWOTRAN, a point kernel code QAD and a Monte Carlo code MORSE.<BR>The accuracies of these calculations were investigated through the analysis of various shielding experiments: the shield tank experiment of the Nuclear Ship "Otto Hahn", the shielding mock-up experiment for "MUTSU" performed in JRR-4, the shielding benchmark experiment using the <SUP>16</SUP>N radiation facility of AERE Harwell and the shielding effect experiment of the ship structure performed in the training ship "Shintoku-Maru". The values calculated by the ANISN agree with the data measured at "Otto Hahn" within a factor of 2 for fast neutrons and within a factor of 3 for epithermal and thermal neutrons. The &gamma;-ray dose rates calculated by the QAD agree with the measured values within 30% for the analysis of the experiment in JRR-4. The design values for "MUTSU" were determined in consequence of these experimental analyses.

著者

森田 定市

出版者

一般社団法人 日本原子力学会

雑誌

日本原子力学会誌 (ISSN:00047120)

巻号頁・発行日

vol.12, no.12, pp.725-731, 1970-12-30 (Released:2010-04-19)

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It is far from easy to find sites suitable for the construction of nuclear power plants even in a country like Japan surrounded by the sea. On the other hand the rising living standards and the rapid development of our industries necessitate, more than ever the supply of more abundant electric power at less cost. It appears to be the established fact that with the expected development of FBR, the power supply of the future will have to rely largely on nuclear power plants, and that in Japan such plants will have to be constructed, whether we like it or not, under the water near the power consuming areas.

著者

土井 和巳

出版者

一般社団法人 日本原子力学会

雑誌

日本原子力学会誌 (ISSN:00047120)

巻号頁・発行日

vol.22, no.8, pp.543-550, 1980-08-30 (Released:2009-03-31)

参考文献数

8

被引用文献数

1

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Japan is located on the “Circum-Pacific Arc”, which is a geoscientifically difficult area for selecting sites suitable as repositories for isolating radioactive waste.The writer has analyzed the problems relevant to radioactive waste isolation in this aqueous and active structural territory, with a view to examining the possibility of finding geological formations suitable for such repositories.As a result, cirtain parts in Neogene sedimentary rocks and Palaeozoic calcarious rocks were found to present geological characteristics that appeared favorable for radioactive waste isolation, while, on the other hand, the study indicated that much difficulty would be foreseen in crystalline rocks such as are currently suitable in the U.S. and in Europe for high level radioactive waste isolation.

著者

野口 宏 松井 浩 吉田 芳和

出版者

一般社団法人 日本原子力学会

雑誌

日本原子力学会誌 (ISSN:00047120)

巻号頁・発行日

vol.24, no.5, pp.381-389, 1982-05-30 (Released:2010-01-08)

参考文献数

16

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In appropriate evaluation of the internal dose of a population due to radioiodine released from a nuclear power plant during normal operation, it is necessary to clarify behavior of radioiodine in the environment. Sunlight appears to be one of the major factors in the chemical form changes, particularly for radioactive methyl iodide.In the present work, photodissociation of gaseous methyl iodide and production of elemental iodine and other iodine species under the sunlight-simulated white light from a xenon lamp in various atmospheric conditions were studied. Methyl iodide dissociated exponentially with the product of the intensity of light and the irradiation time. The dissociation of methyl iodide produced mainly elemental iodine, and other iodine species (e.g. particulate iodine) up to about 10% in relatively low concentration (less than 10-9g/cm3) of methyl iodide. The effect of relative humidity on the reaction was not observed.

著者

中島 篤之助 高橋 正雄 森下 益孝

出版者

一般社団法人 日本原子力学会

雑誌

日本原子力学会誌 (ISSN:00047120)

巻号頁・発行日

vol.3, no.2, pp.104-109, 1961

被引用文献数

2

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Two procedures are described for the sensitive spectrographic determination of 0.023 ppm of boron in graphite for nuclear reactor. In the first method, preliminary concentration is carried out by the removal of the graphite by ashing in the presence of La₂O₃. Then the contents of boron in La₂O₃ are determined by the carrier-distillation method. In the second method, the sample in the form of powder is compressed into pellets with the aid of a phenol-formaldehyde resin as binding medium, and these are arced at 7 A (d.c.). By means of display microphotometry, the peak height of B at 2497.73 &Aring; is compared with that of the NO(&gamma;) band component at 2497.14 &Aring;.

著者

尾本 彰 杉崎 利彦 長坂 秀雄

出版者

一般社団法人 日本原子力学会

雑誌

日本原子力学会誌 (ISSN:00047120)

巻号頁・発行日

vol.28, no.10, pp.950-956, 1986

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Many integral and separate effect experiments have been carried out cooperatively by the Japanese BWR utilities and vendors. Through these results, various counter-current-flow limitation phenomena occurring inside the BWR core, steam and mist cooling effect, multibundle effect etc. have been identified effectively to cool down the core during LOCA transients.<BR>Based on these findings and with other aids, SAFER code, which can better estimate the thermal-hydraulics of the BWR transient by the simple one-dimentional method, has been developed by the BWR vendors to replace with the existing SAFE-REFLOOD-CHASTE code system. <BR>The new code predicts the peak-cladding-temperature for the standard jet-pump BWR LOCA transients to be as high as 500600&deg;C, which is well below the current regulatory limitation. LOCA/ECCS constraints will be reduced for future BWR core managements and ECCS equipments surveillance etc. by the use of new code.

著者

岡 芳明 村尾 良夫 星 蔦雄 尾本 彰 田畑 広明 水町 渉 守屋公 三明 久木 田豊 鈎孝 幸 牧原 義明 玉置 昌義

出版者

一般社団法人 日本原子力学会

雑誌

日本原子力学会誌 (ISSN:00047120)

巻号頁・発行日

vol.37, no.9, pp.766-795, 1995

被引用文献数

1

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21世紀に予想される後進国での電力需要の急上昇および各国での労働力不足に対処するため,国内外で省力化と人にわかりやすい技術に基づく次世代軽水炉を開発するプロジェクトが進められている。このような状況を踏まえて,次世代軽水炉の開発そして研究状況,そこに使用されている新しい要素技術についてまとめておくことは,会員に最新の情報を提供するという観点から有意義である。本稿では,次世代BWR, PWRおよび他の軽水炉の開発・研究状況および新要素技術について述べる。

著者

服部 禎男

出版者

一般社団法人 日本原子力学会

雑誌

日本原子力学会誌 (ISSN:00047120)

巻号頁・発行日

vol.10, no.5, pp.278, 1968

著者

服部 禎男 根本 和泰 石田 健二 御園生 淳 菅沼 浩敏 石井 敬一郎 山岡 聖典

出版者

一般社団法人 日本原子力学会

雑誌

日本原子力学会誌 (ISSN:00047120)

巻号頁・発行日

vol.32, no.7, pp.688-696, 1990

被引用文献数

1