Title of article
Considerations for in-service inspection on pressure vessel of 200MW nuclear heating reactor Original Research Article
Author/Authors
Huajian Chang، نويسنده , , Shuyan He، نويسنده , , Junjie Liu، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2000
Pages
6
From page
11
To page
16
Abstract
The 200MW nuclear heating reactor adopts an integrated arrangement for the primary circuit. It is designed to be operated at lower temperature and lower pressure as compared to large reactors. A steel containment serves a barricade for the reactor pressure vessel. The pressure vessel has some safety characteristics, such as low stress level, low induced integral neutron flux, and high toughness etc. Among them, the most important is its LBB behavior. Based on the safety analysis for the pressure, the requirements and procedures of in-service inspection are layed-out accordingly.
Journal title
Nuclear Engineering and Design Eslah
Serial Year
2000
Journal title
Nuclear Engineering and Design Eslah
Record number
889220
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