Search by Bookstore
Holdings of Libraries in Japan
This page shows libraries in Japan other than the National Diet Library that hold the material.
Please contact your local library for information on how to use materials or whether it is possible to request materials from the holding libraries.
other
JOPSS:JAEA Originated Papers Searching System
DigitalYou can check the holdings of institutions and databases with which Institutional Repositories DataBase(IRDB)(Institutional Repository) is linked at the site of Institutional Repositories DataBase(IRDB)(Institutional Repository).
Search by Bookstore
Bibliographic Record
You can check the details of this material, its authority (keywords that refer to materials on the same subject, author's name, etc.), etc.
- Material Type
- 規格・テクニカルリポート類
- Author/Editor
- 飯塚 透上出 英樹西村 元彦
- Publication Date
- 1998-07
- Publication Date (W3CDTF)
- 1998
- Alternative Title
- Large-scaled thermohydraulic tests plan for cooling systems in fast reactors; Effect of secondary piping structure on dynamics
- Periodical title
- PNC TN9410 98-083
- Target Audience
- 一般
- Note (General)
- 出版タイプ： NA実証炉段階で採用される原子炉冷却系に係る新概念技術の確立を目的とし、原子炉容器から蒸気発生器(SG)までを総合的に模擬した大型ナトリウム試験(原子炉冷却系総合試験)計画を検討した。これまでに基本設計を行い、試験施設は実証炉の1/3縮尺2ループモデルとした。SGについては水・蒸気側の模擬性を高めるため高さ方向1/1縮尺の部分モデルとし、2次系配管を1ループに集約して接続するものとした。このため、2次系配管が著しく長くなり、実機模擬性が損なわれる可能性が考えられる。また、2次系配管の途中で2ループを1ループに集約する構造のため、自然循環試験時にはループ間のアンバランスが助長されることも考えられる。そこで、2次系配管長をパラメータとして動特性解析を実施し、模擬性に与える影響を把握した。また、IHX伝熱面積等にループ間で差異を与えた場合の予測解析を実施した。その結果、SGが流れ方向に長く、熱容量も大きいことから、2次系配管長の影響は相対的に小さいことが分かった。また、片方のループにのみ選択的に自然循環が発達するような現象は見られなかった。以上より、2次系配管長の短縮は制約条件が厳しい割に熱過渡の改善の効果が小さく、構造上可能な範囲すべきことが分かった。また、ループ間に実証炉と同等の製作誤差があっても、試験の実施及び試験結果の評価に大きな影響を与えるような問題は生じないことが分かった。Large-scaled thermohydraulic tests are planned for new key technologies in the heat transport systems of a demonstration fast reactor. The test facility is consisted of components from a reactor vessel to a steam generator (SG). Basic design of the large-scaled thermohydraulic test facility is 1/3 scale of the demonstration fast reactor with two primary cooling loops and two into one secondary loop. The secondary piping length of the test facility is longer than the 1/3 scale of the demonstration fast reactor. The tests facility has the branch and junction of the secondary piping because of two primary loops and one SG. There is a possibility of flow and temperature unbalance if a buoyancy force were large and pressure loss were small. Therefore, dynamics analyses of the thermal transition tests had been done in which the secondary piping length. To examine the unbalance occurred or not, the natural circulation analysis had been performed providing different heat transfer area of the IHX or presser loss of the primary loop between A loop and B loop. It was shown from the analyses that the temperature response during the transition was delayed in the test model compared to the real reactor. Main cause of the delay was due to the real scaled SG. Other parameters, the length of piping etc., were not very influential to the response. The analysis such predicted that there wasn't large difference of global behaviors between the loops. Therefore, it was shown that there would be no problem, if the difference were made between the loops due to a manufacturing error.
- Source
- /PNC-TN9410-98-083.pdf （fulltext）