巻号一覧
後続誌
37 巻, 4 号
選択された号の論文の8件中1～8を表示しています
- |<
- <
- 1
- >
- >|
-
深堀 智生, 千葉 敏, 高田 弘, 中原 康明, 渡辺 幸信1995 年 37 巻 4 号 p. 264-273
発行日: 1995/04/28
公開日: 2010/01/08
ジャーナル フリーPresent status of a research on intermediate energy nuclear data, which are required for various applications, are reported. As an important foundation for data evaluation at intermediate energy region, nuclear reaction theories and models such as the preequilibrium model, intranuclear cascade model, quantum molecular dynamics, optical model potential and fission model, are reviewed. The model calculation codes are having been developed based on these theories and models. Status of these codes and results of a few benchmark tests are also described as well as the status of production of evaluated intermediate energy nuclear data files and improvement of hadron transport theories.抄録全体を表示PDF形式でダウンロード (2468K) -
服部 禎男1995 年 37 巻 4 号 p. 274-282
発行日: 1995/04/28
公開日: 2009/04/21
ジャーナル フリー10年あまり前に提示されたT.D. Luckey博士の「放射線ホルミシス」の主張に対して,電力中央研究所は科学的真実を求めて調査と動物実験などを始めた。第1フェーズの検討によって多くの興味あるデータを得て,いま全国の大学などの専門家の協力によって,研究はその第2フェーズに入っている。本稿では,これまでの知見と分析から,低レベル放射線と人体のかかわりについて述べる。
幸運なことにDNAの分析,遺伝子の研究が急激な発展をしつつある時に,ホルミシス研究を立ち上げたためにそのメカニズムの解明が予想外の速度で進展する気配をみせている。生化学,分子生物学,免疫学,がんの機構解明など,従来の放射線基礎医学の先生方に加えて広範囲の先生にご指導を仰いで,生命のメカニズムの本質に触れるような議論も登場している。本年(1995年)秋には,米国NIHやEPAの専門家を含めた国際シンポジウムも計画され,研究の進展によって多くのデータが得られるにつれ,この研究の重要性がいよいよ拡大しつつあるように思われる。抄録全体を表示PDF形式でダウンロード (549K) -
武谷 清昭1995 年 37 巻 4 号 p. 283-290
発行日: 1995/04/28
公開日: 2009/04/21
ジャーナル フリー今後,東アジアで急増するエネルギー需要に応えるための化石燃料の燃焼を阻止し,その代替として核エネルギーを活用し電力および熱を供給できる安全性の高い小型原子炉システムの実用化の完成を,我が国の国際貢献の立場からも,推進することを提案している。この原子炉システムは,地球上に点在するエネルギー需要地で安全かつ容易に運転できる。これの完成を我が国の原子力戦略の一つとし,あわせて我が国の原子力界の活性化とGNPの増大をも期待したい。抄録全体を表示PDF形式でダウンロード (3054K) -
豊田 正敏1995 年 37 巻 4 号 p. 291-302
発行日: 1995/04/28
公開日: 2010/01/08
ジャーナル フリーBased on the recognition that layout elements of a repository are important factors to govern total costs of the high-level radioactive waste disposal, the study on their feasibility has made as a trial from the view points of economics, shielding, strength against pressure, retention capability and especially mechanical interactions within near-field under some premises and conditions discribed below to establish an economical and rational repository concept.
(1) Host rocks: Granite (800m deep) and sedimentary (500m deep)
(2) Emplacement methods: Horizomtal
(3) Thickness of overpacks: 20cm
(4) Thickness of bentonite: 70cm
(5) Inner diameter of repository tunnel: 2.3m
(6) Center distance betweem repository tunnels: 20m
In addition, perceiving long-term behaviors of near field composed of waste package, overpack. bentonite and surrounding rock, some suggestions or tasks for each items above are also referred.
Among assumptions for these studies, there are some items, such as corrosion rate and performance of overpack, as well as mechanical properties of bentonite and so on, not comfirmed fully yet by experiments, and so studies are made under conservative assumptions for these items. Considering study results as a whole, the premises and conditions specified in these studies are concluded to be highly feasible.抄録全体を表示PDF形式でダウンロード (7827K) -
茅野 政道, 石川 裕彦, 山澤 弘実, 永井 晴康1995 年 37 巻 4 号 p. 312-315
発行日: 1995/04/28
公開日: 2009/04/21
ジャーナル フリーPDF形式でダウンロード (4976K) -
国富 一彦, 竹田 武司, 篠崎 正幸, 大久保 実, 丸山 茂樹, 小池上 一1995 年 37 巻 4 号 p. 316-326
発行日: 1995/04/28
公開日: 2010/03/08
ジャーナル フリーThe Intermediate Heat Exchanger (IHX) of the High Temperature Engineering Test Reactor (HTTR) is a helium-helium type heat exchanger with the heat capacity of 10MW. The internal structures such as heat transfer tubes made of Hastelloy XR are used normally at about 930°C because the IHX can supply the secondary helium gas with the maximum temperature of 905°C transferred from the primary helium gas of 950°C. They compose the primary boundary and their creep strain and creep damage evaluated conservatively based on the elastic analysis cannot meet the required criteria with enough margin. The design method based on the complete creep analysis was used for the primary coolant boundary components.
This report describes an evaluation procedure based on the creep analysis and its results. The results show that the creep strain and creep damage increased rapidly during a few initial cycles, however, increased far less after that. The results can meet the design limit for 105h of the HTTR life time.抄録全体を表示PDF形式でダウンロード (4699K) -
石田 政義, 村上 朋子, 川島 克之, 渡 孔男, 中尾 昇, 三浦 正憲1995 年 37 巻 4 号 p. 327-337
発行日: 1995/04/28
公開日: 2009/04/21
ジャーナル フリーNumerical simulation of an unprotected loss-of-flow( ULOF) accident has been performed for a large liquid-metal-cooled fast breeder reactor (LMFBR) equipped with gas expansion modules (GEMs) in the radial periphery of the reactor core. The effectiveness of the GEMs in small fast reactors was demonstrated already in the passive safety testing in the Fast Flux Test Facility. According to neutronic calculations based on the transport theory, even in large reactors of electrical power 600 to 1, 300 MW, the reactivity worth of GEMs, which replace one layer of radial blanket fuel subassemblies, ranges from -1.9 to -1.4, depending on the size of the core. A simulation of ULOF transient was performed with a 5.5s flow-halving time in a 600 MWe LMFBR equipped with GEMs of -1.9$ reactivity worth. The result showed that, if 10% of the rated core coolant flow by pony motors was available following the main pump coastdown, the GEM reactivity alone could bring the reactor subcritical and the predicted maximum coolant temperature was substantially lower than the sodium boiling point. The reactivity worth calculations, a modeling of gas expansion behavior, and ULOF simulation together with needs of further development for the GEM application are described.抄録全体を表示PDF形式でダウンロード (3102K) -
中島 邦久, 柴山 環樹, 茅野 秀夫1995 年 37 巻 4 号 p. 338-345
発行日: 1995/04/28
公開日: 2010/01/08
ジャーナル フリーA new mechanical dispersion process to produce oxide dispersion strengthened (ODS) vanadium alloy has been successfully developed. In order to study effects of irradiation on microstructural evolution in ODS V alloy and unalloyed V, transmission electron microscopy observation and Vickers microhardness test were performed. ODS V alloy has five times as large Vickers microhardness as unalloyed V. ODS V alloy has twin structure. After irradiated with 3 MeV Au2+ ions up to 1.5×1020 ions/mm2 (about 60dpa) at 813 K, microcrystalline transformation and defect clusters were observed in unalloyed V. On the other hand, the twin structure was stable in ODS V alloy. After irradiated up to 6.Ox1020 ions/mm2 (about 250 dpa), many microvoids were observed in unalloyed V, while the twin structure in ODS V alloy was disappeared. However no voids could be observed in ODS V alloy. Postirradiation anneal hardening was observed in unalloyed V after irradiated by neutrons up to 8.3×1022n/mm2(En> 1 MeV, 144 h). Nevertheless no radiation anneal hardening could be observed in ODS V alloy. Therefore ODS V alloy has a significant resistance to irradiation damage.抄録全体を表示PDF形式でダウンロード (12977K)
- |<
- <
- 1
- >
- >|