文献一覧: 斉藤鉄夫 (著者)

2 0 0 0 鉄筋圧接部の超音波探傷試験の実用化に関する研究 : 構造系

著者: 藤盛紀明斉藤鉄夫
出版者: 一般社団法人日本建築学会
雑誌: 学術講演梗概集. 構造系
巻号頁・発行日: vol.52, pp.1165-1166, 1977-10

2021-10-04 23:47:04
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https://ci.nii.ac.jp/naid/110004135011

1 0 0 0 OA 固体中の弾性波伝搬

著者: 春海佳三郎斉藤鉄夫
出版者: The Institutew of Noise Control Engineering of Japan
雑誌: 騒音制御 (ISSN:03868761)
巻号頁・発行日: vol.2, no.6, pp.32-36, 1978-12-01 (Released:2009-10-06)
参考文献数: 11

2023-07-20 10:04:39
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1 0 0 0 直ダクト付きγ線しゃへい用コンクリート壁に組み込む補償しゃへい体の設計手法および線量率分布の測定と解析

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

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.

2021-10-04 23:49:08
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1 0 0 0 放射線輸送計算コードを用いた「むつ」舶用炉のしゃへい解析法と実験解析に基づく評価

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

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 γ-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.