日本原子力学会誌

医療用重粒子加速器の現状

河内清光

1996 年 38 巻 8 号 p. 650-657
発行日: 1996/08/30
公開日: 2009/04/21

DOIhttps://doi.org/10.3327/jaesj.38.650

ジャーナルフリー

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放射線治療は,がん治療にとって極めて有効な手段で,治療後の患者のQuality of Life (QOL)を考えれば,これに優るものはない。最近では,さらに治癒率の向上と,治癒の質の向上を目指して陽子線を含む重荷電粒子線治療に大きな関心が寄せられ,世界中でこの治療を受けた患者数は2万人を超えている。
放射線医学総合研究所では,重イオン治療の臨床試行を開始し,その成果も徐々に公開されるとともに,臨床試行の経験も踏まえて,装置や治療技術の高度化も着々と進めている。一方,国内外において,陽子線や重イオンの医療装置の建設や開発計画が進められており,それらの現状を紹介する。

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高温用加圧水冷却器の管外熱伝達相関式の高精度化

国富一彦, 竹田武司, 今西克臣, 大久保実, 溝上頼賢, 原輝夫, 菊池洋

1996 年 38 巻 8 号 p. 665-672
発行日: 1996/08/30
公開日: 2010/03/08

DOIhttps://doi.org/10.3327/jaesj.38.665

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A primary pressurized water cooler (PPWC) with reverse-U type heat transfer tubes in the High Temperature Engineering Test Reactor (HTTR) cools the primary helium gas of 950°C from the reactor to approximately 400°C and its design heat capacity is 30MW. However, the heat transfer characteristics of the PPWC were not proven in detail because only a little experience about its design and construction has been obtained.
The heat transfer correlations on the shell side were experimentally obtained by a 1/2 scale simulation test apparatus of the PPWC to improve design accuracy. These correlations can consider the effects of flow pattern around baffle plates, a seal mechanism to prevent by pass flow and an impingement plate with many small holes to improve heat transfer characteristics.

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武蔵工大炉医療用照射場の中性子ビーム設計

松本哲男

1996 年 38 巻 8 号 p. 673-682
発行日: 1996/08/30
公開日: 2010/01/08

DOIhttps://doi.org/10.3327/jaesj.38.673

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Design studies were carried out for the Musashi reactor (TRIGA-II, 100kW) with a view to generating epithermal and thermal neutron beams applicable to boron neutron capture therapy (BNCT). By Monte Carlo calculations, the thermal neutron beam intensity 1.1×10⁹n/cmcm2·s and the epithermal neutron beam intensity 4.1×10⁸n/cmcm2·s at the operation power of 100kW have been obtained at the irradiation ports in the thermal and thermalizing columns, respectively. These beams are little adulterated with fast neutrons and gamma-rays, and are relatively forward-directed. Depth-dose calculations in a tissue phantom showed that above thermal and epithermal neutron beams would be useful to treat superficial (-4cm) and deeper (-6.5cm) tumors, respectively. The full-dose treatment time is estimated about 2.5h. These neutron beam designs suggest how TRIGA reactors could be modified for BNCT, and the produced neutron beams, if built into the Musashi reactor, will significantly increase the chance of success of BNCT in Japan.

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原子力開発における信頼形成過程に関するベイズ的考察

山形浩史, 神田啓治

1996 年 38 巻 8 号 p. 683-688
発行日: 1996/08/30
公開日: 2010/01/08

DOIhttps://doi.org/10.3327/jaesj.38.683

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The sodium leak accident of MONJU, a fast breeder reactor that Power Reactor and Nuclear Fuel Development Corporation (PNC) has operated since 1995 in Japan, and the PNC's management of the accident have created the public distrust not only in the safety of MONJU but also in the nuclear development policy of Japan. In order to learn a lesson from these and to establish a relationship of mutual trust with the public, this paper simulates process of the public reliance in cases of an accident, no accident, a cover-up, and so on. In this paper the public reliance is defined as the conditional probability that the nuclear reactor is safe given the state of information that the public has. The conditional probability is estimated by using the Bayes' Theorem. The simulation shows that (1) we lose the public reliance by only one accident, recover it by a many-year safe operation, but never by a cover-up, and (2) the more information we open to the public, the better relationship of mutual trust with the public we would establish, especially in an early stage of operation.

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