書誌事項
- タイトル別名
-
- Countermeasure against Thermal Fatigue Crack of Primary Loop Recirculation Pump in BWR
- ゲンシロ サイジュンカン ポンプ ネツ ヒロウ ワレ タイサク
この論文をさがす
抄録
The reactor water was fed to the purge water of the mechanical seal on the original design of the primary loop recirculation pump. Because the mechanical seal had a short life due to the cruds in the reactor water, the clean purge water was adopted instead of the reactor water. After this modification, the shallow cracks were found on the surface of the pump shaft and casing cover due to the temperature fluctuation between the cold purge water and the hot pump discharge water. The fundamental mechanism and countermeasure were investigated by scale test, mock-up test and so on. The flow barrier with a heater was contrived through these tests. It has been introduced gradually in operating and constructing PLR pumps after its completion in 1995. The PLR pumps are overhauled around every 10 years in Japan. The first overhaul of the PLR pumps showed no cracks around the pump shaft and casing cover after 10 years' operation. This paper presents both its development process and inspection results.<br>
収録刊行物
-
- 日本原子力学会和文論文誌
-
日本原子力学会和文論文誌 7 (4), 338-349, 2008
一般社団法人 日本原子力学会
- Tweet
キーワード
- primary loop recirculation pump
- purge water of mechanical seal
- thermal fatigue cracks due to temperature fluctuation
- fundamental mechanism investigation and countermeasure by scale and mock-up tests
- flow barrier with heater to prevent the temperature fluctuation
- inspection results after 10 years' operation
詳細情報 詳細情報について
-
- CRID
- 1390282680162906496
-
- NII論文ID
- 10024631963
-
- NII書誌ID
- AA11643165
-
- ISSN
- 21862931
- 13472879
-
- NDL書誌ID
- 9732440
-
- 本文言語コード
- ja
-
- データソース種別
-
- JaLC
- NDL
- Crossref
- CiNii Articles
-
- 抄録ライセンスフラグ
- 使用不可