平成7年度 リサイクル試験炉開発プログレスレポート

• Material Type: 文書・図像類
• Title: 平成7年度 リサイクル試験炉開発プログレスレポート
• Author/Editor: 笠井 重夫; 戸澤 克弘; 赤津 実; 小川 伸太; 渡辺 一郎; 早船 浩樹; 永沼 正行; 一宮 正和; 林 秀行; 向坊 隆一
• Author Heading: 笠井 重夫; 戸澤 克弘; 赤津 実; 小川 伸太; 渡辺 一郎; 早船 浩樹; 永沼 正行; 一宮 正和; 林 秀行; 向坊 隆一
• Publication Date: 1996-07
• Publication Date (W3CDTF): 1996-07
• Alternative Title: JFY 1995 Progress report of the development on the actinide recycle test reactor(ARTR)
• Periodical title: PNC TN9430 96-004
• Text Language Code: jpn
• Target Audience: 一般
• Note (General): リサイクル試験炉開発における平成7年度の概念設計について報告した。また,概念構築上重要な要素研究として,試験炉での炉内計装技術の調査と引抜型UISにおける機器再使用性を検討し,開発課題を示した。リサイクル試験施設との隣接設置,試験炉での試験内容及び試験炉の運用スケジュールを想定して,試験炉全体の輪郭を示した。次年度の計画も記述した。1)概念の詳細化,2)前提条件の確認,3)実用リサイクル炉概念の開発,4)試験炉での試験シミュレーション。; Authors are studying the Actinide Recycle Fast Breeder Reactor (named ARFBR in this paper), which contribute to the reduction of burdens to environments and to enhance the capability to prevent the nuclear proliferation as the entire nuclear recycle system (named Advanced Fuel Recycling FBR system (AFRFS) in this paper), and also investigating the ARTR for developing the ARFBR. The investigation of the ARTR consists of the design study of the ARTR and R\&Ds of key technology existing in ARTR concept. The conceptual design study of the ARTR is planed to be conducted for 2 years from 1995 to 1996 as first stage. 1995's design study have been performed with drawing over all plant concept with supposing various tests in reactor and usage of reactor. Followings are distinctive feature of 1995's design study. (1)Maximum reactor power is 400MWt with about 1.6m diameter irradiation (burning) cores, which are designed to be operated up to 150GWd/t as average burn up. Maximum core diameter is about 2.5m for low power nuclear physics tests which are designed to be able to estimate characteristics of large scale core by using the test results. (2)Mixed oxide (MOX) and Mixed nitride (MN) core is designed respectively to be able to be used for static nuclear physics test, for nuclear and thermal transient test, and for full power irradiation or burning test. Each core is designed to terminate ATWS events passively, with using GEM for MOX core and with using spectral adjustment for MN core. (3)Fuel assembly is employed ductless type which is a promising candidate for the ARFBR. Sizing of a fuel assembly is determined in basis on MOX fuel design because MOX fuel pin length covers MN fuel pin which accommodates lesser FP gases because of its lower temperature. Fuel assembly is managed to be held by hydraulic force in case of freeing mechanical stopper by requirement of testability. (4)Reactor assembly is designed based on so called Head Access Loop Type Reactor. Main changes ...
• Source: /PNC-TN9430-96-004.pdf （fulltext）; https://jopss.jaea.go.jp/pdfdata/PNC-TN9430-96-004.pdf
• Access Restrictions: 限定公開
• Data Provider (Database): 国立情報学研究所 : 学術機関リポジトリデータベース（IRDB）（機関リポジトリ）; https://irdb.nii.ac.jp
• Original Data Provider (Database): 日本原子力研究開発機構 : JOPSS:JAEA Originated Papers Searching System

• Summary, etc.: リサイクル試験炉開発における平成7年度の概念設計について報告した。また,概念構築上重要な要素研究として,試験炉での炉内計装技術の調査と引抜型UISにおける機器再使用性を検討し,開発課題を示した。リサイクル試験施設との隣接設置,試験炉での試験内容及び試験炉の運用スケジュールを想定して,試験炉全体の輪郭...