巻号一覧
後続誌
19 巻, 8 号
選択された号の論文の7件中1～7を表示しています
- |<
- <
- 1
- >
- >|
-
長谷川 明, 高野 秀機, 中川 正幸1977 年 19 巻 8 号 p. 508-519
発行日: 1977/08/30
公開日: 2009/03/31
ジャーナル フリー最近,さまざまな分野で話題にされているベンチマーク・テスト計算について,高速炉系の核計算における核データの流れの中でのベンチマーク・テストをとりあげて解説する。評価済み核データ・ファイルの適用性評価を目的として行われる積分実験データに基づくベンチマーク・テストを中心に,その応用としての断面積修正への適用,さらに実験とは離れて標準問題を設定して計算手法や使用核データ間の差異を明らかにするための国際ベンチマーク・テストまでを取り上げる。抄録全体を表示PDF形式でダウンロード (913K) -
広瀬 保男, 梶山 万四郎, 大井 昇1977 年 19 巻 8 号 p. 520-525
発行日: 1977/08/30
公開日: 2009/03/31
ジャーナル フリーThe Nuclear Fuel Development (NFD) hot labaratory was designed and constructed for post-irradiation examination of a full length light water reactor fuel assembly, which has radioactivity of about 1 million curie. The main structure consists of seven concrete β-γ cells, an isolation area and a 13 m deep water pool which is devided into a storage pool and an examination pool with a underwater view window. Floor space is 2, 900 m2 and about 70% is radiation control area. An emphasis of the layout was laid particularly on material flow in the laboratory: a manipulator-crane, underwater transport device for fuel assembly and so on, were developed. A fuel assembly is to be transported into this facility by a truck cask which weigh less than 27 tons. The cask is lowered in the examination pool for unloading fuel assembly. The fuel assembly or disintergrated fuel rods can be transfered to the monitoring cell for detailed examinations. The safety analysis of the facility, some experience on the construction and the licensing are also briefly discussed.抄録全体を表示PDF形式でダウンロード (2662K) -
渡辺 斉, 栗原 正義1977 年 19 巻 8 号 p. 526-529
発行日: 1977/08/30
公開日: 2009/03/31
ジャーナル フリーFor evaluating the feasibility of advanced fuels such as carbides, carbonitrides and nitrides, JAERI has built a new Plutonium Fuel Research Facility at the O-arai site in Jan. 1974. The total floor space is about 1, 500 m2. Most of equipments and glove boxes have been made by the end of 1976.
The glove boxes in which Ar gas is circulated, are used for preparing the fuel pellets. On the other hand, the ordinary air atmosphere glove boxes are used for ceramography, Xray diffraction, chemical analysis and measuring physico-chemical properties. The pressure regulation of the former glove boxes is more troublesome than the latter. In order to obtain easy handling and to keep the negative pressure, two types of the pressure control device are equipped on Ar gas atmosphere glove box; One is the proportional-integration control device and the other the open-close control device. The limit of pressure control is -30±20 mm H2O. The remaining impurities are maintained less than 2 ppm oxygen and 3 ppm water.
Various kinds of safety equipment for Pu handling are also installed, including confinement, criticality, radiation exposure and physical protection.抄録全体を表示PDF形式でダウンロード (2637K) -
榎本 穣1977 年 19 巻 8 号 p. 530-534
発行日: 1977/08/30
公開日: 2009/03/31
ジャーナル フリーFukushima Daiichi Nuclear Power Station Unit-3 is a BWR unit located in the seaside area of Okuma town in Fukushima Prefecture. Its thermal output is 2, 381 MWt; and the electrical rating is 784 MWe. The construction at the site started in Aug. 1970; and the commercial operation began on Mar. 27, 1976. The plant has been operated satisfactory and was shutdown Mar. 1, 1977 for the first annual inspection outage.
Here are the summary of the plant facility and the operating experience.抄録全体を表示PDF形式でダウンロード (4397K) -
竹永 睦生, 山本 理, 山下 忠興1977 年 19 巻 8 号 p. 543-549
発行日: 1977/08/30
公開日: 2009/03/31
ジャーナル フリーLithium borate (Li2B4O7) is known as one of the most promising thermoluminescence materials because of its low dependence on photon energy. A new phosphor, Li2B4O7 activated with copper and silver (0.02_??_Cu, 0.02_??_Ag), has been developed and found to have the following thermoluminescence characteristics.
(1) Its thermoluminescence emission bands lie in the near ultraviolet region; a dominant peak appears at 368 mμ (by Cu) and another smaller one at 268 mμ.
(2) The main thermoluminescence glow peak appears at 185°C (by Ag), and another smaller one at 110°C.
(3) The thermoluminescence output detected by a widely used photomultiplier (1P21) is about 3 times larger than that of Li2B4O7: Mn, and the expoure response is linear in an exposure range from 10 mR to 300R.
(4) Fading is less than 9% in 2 months.抄録全体を表示PDF形式でダウンロード (495K) -
U-235分析計の製作とその性能試験園部 次男, 落合 健一, 朝倉 祥郎, 中村 久, 堤 健一, 相原 亘, 高畑 重弘, 山内 洋, 下村 丁一1977 年 19 巻 8 号 p. 550-554
発行日: 1977/08/30
公開日: 2009/03/31
ジャーナル フリーA 235U enrichment analyzer based on the interference spectrometry has been designed and fabricated as compactly as possible. The analyzer is composed of an emission source, an optical system and a detection system. The source is a water cooled hollow cathode tube and a 100 mg pellet of UO2 sample is placed in the cathode. The spectrometer of 0.5 m, a Czerny-Turner type is used with a built-in Fabry-Perot etalon. The pressure of nitrogen in the Fabry-Perot etalon is repeatedly scanned by leaking the gas through an electro-magnetic valve which is operated by the electric signal from a pressure transducer. The two-isotope components of uranium line 5, 027.4Å are well separated by the etalon with a spacer thickness of 0.25 cm. A relative standard deviation of 0.92.2% was obtained for the samples containing 0.55.0% of 235U. The relative errors of the results obtained by this analyzer were less than 1.3% for UO2 pellets of nuclear fuels.抄録全体を表示PDF形式でダウンロード (2076K) -
1977 年 19 巻 8 号 p. 555-556
発行日: 1977/08/30
公開日: 2009/03/31
ジャーナル フリーPDF形式でダウンロード (241K)
- |<
- <
- 1
- >
- >|