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33 巻, 6 号
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吉川 潔1991 年 33 巻 6 号 p. 530-538
発行日: 1991/06/30
公開日: 2010/04/19
ジャーナル フリーPDF形式でダウンロード (9864K) -
中村 尚司, 平山 英夫1991 年 33 巻 6 号 p. 539-548
発行日: 1991/06/30
公開日: 2010/04/19
ジャーナル フリーThe shielding design study for high energy (beam energy higher than 100MeV) accelerator facilities is perfofmed on beam loss estimation, estimation of radiation source, bulk shielding calculation for beam dump and building wall, dose estimation of surrounding environment due to skyshine, streaming calculation through duct and labyrinth, induced radioactivity estimation.
Here, among of these items, we describe the present studies and the future subjects on the estimation of radiation source and the shielding calculation for beam dump and building wall in both cases of electron and ion accelerators.抄録全体を表示PDF形式でダウンロード (2864K) -
HENDEL多チャンネル試験装置によるクロス流れ試験結果高瀬 和之, 日野 竜太郎, 宮本 喜晟1991 年 33 巻 6 号 p. 564-573
発行日: 1991/06/30
公開日: 2010/04/19
ジャーナル フリーThe multi-channel test rig (T1-M) of the fuel stack test section in a helium engineering demonstration loop (HENDEL) is a large-scale experimental facility which simulates one fuel column of the HTTR core.
A crossflow test was carried out using the T1-M. The objective of this test is to investigate the thermal and hydraulic characteristics in the fuel stack under the conditions that produced the crossflow through a gap from the outside of the graphite blocks into twelve coolant channels. The crossflow was forcibily produced by a parallel gap situated between the third and fourth blocks from the top of those in the heated section mounted in the vertical direction.
The crossflow was 43-56% of the total flow rate of helium gas in T1-M for heated flow and 5-37% for isothermal flow, and that became more in an outer channel of Nos. 7-12 channels than in an inner channel of Nos. 1-6 with decreasing the gap width. Also it was found that the crossflow affected a redistribution of flow rate flowing into the ch nnels and a temperature distribution of the fuel rod.抄録全体を表示PDF形式でダウンロード (567K) -
芝本 真尚, 柳原 敏, 助川 武則, 田中 貢1991 年 33 巻 6 号 p. 574-584
発行日: 1991/06/30
公開日: 2010/04/19
ジャーナル フリーCollective external dose in the dismantling of the Japan Power Demonstration Reactor (JPDR; BWR, 90MWt) was estimated. Radioactive inventories of components to be dismantled were first evaluated using the operation history of the JPDR. Dose equivalent rate at each working area was calculated on the basis of the obtained radioactive inventories. To evaluate man-hours relating to the JPDR dismantling in radiation environment, the dismantling activities were further categorized to be preparation, dismantling, packaging, shipping and cleaning up, and man-hours Were calculated according to occupations such as a dismantling worker, a superviser and a radiation officer. Through these studies, collective external dose was evaluated to be approximately 300 man-mSv, which is relatively small compared with that of external dose is useful in comparison with the actual value.抄録全体を表示PDF形式でダウンロード (6402K) -
ボイド率へのスペーサの影響および クロスフローを無視した解析師岡 慎一, 白川 健悦, 石塚 隆雄, 吉村 邦広, 馬渡 勝彦1991 年 33 巻 6 号 p. 585-593
発行日: 1991/06/30
公開日: 2010/04/19
ジャーナル フリーVoid measurement of a vertical 4×4 rod bundle has been conducted behind a spacer in a steam-water two-phase flow using an advanced X-ray CT scanner and one-dimensional single subchannel analysis without a cross-flow was done. It was found from the experimental results that the cmss-sectional averaged void fraction data behind the spacer could be predicted by the drift-flux model, that the spacer has a negligible effect on the cross-sectional averaged void fraction and that EPRI correlation made it possible to accurately predict the void data. In addition, the simplified single subchannel analysis without the cross-flow between subchannels gave good agreement with data of center subchannels in a quality range of 5% or more. However, the analysis predicted higher void fraction than experimental results in the corner subchannel.抄録全体を表示PDF形式でダウンロード (4475K) -
福井 正美, 白井 浩之, 来馬 克美, 前川 素一, 飯島 敏哲, 桂山 幸典1991 年 33 巻 6 号 p. 594-602
発行日: 1991/06/30
公開日: 2010/04/19
ジャーナル フリーIt is difficult at present to verify the distribution of radioactivities and to estimate their accumulation trends only from the results of environmental monitoring because of quite low level of effluent from nuclear power plants. Therefore, a mathematical model was developed to support the environmental monitoring as well as to predict the accumulation trends of radioactivities discharged into the environment. Then the model was simulated by applying on the behavior of 60Co released from the nuclear power station located in the coast of Uchiura Bay, a part of Wakasa Bay.
The mathematical expression is composed of an estimation model for distribution of current velocities based on the results of field observations, a diffusion equation including the terms of advection, diffusion, appearance and disappearance, and a box model applied for some reaches. Adsorption on sediment and effect of scavenging are also taken into consideration. Details of the model are described in this paper and the validity is checked and discussed. The results of verification draw the conclusions as follows:
(1) On the concentration of 60Co in the sediment only detectable near the discharge point, the values estimated and observed were agreed within a factor of three.
(2) It was estimated that the half amount of 60Co released during 8yr after 1974 is accumulated in the bay sediment, whereas the other is lost away from the bay.
(3) The results of calculation showing no increase of accumulation at 1982 suggest nonprogressive accumulation in the future.抄録全体を表示PDF形式でダウンロード (2292K)
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