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Aug 1, 2004 · The AP-600, an advanced pressurized-water reactor, utilizes a passive containment cooling system (PCCS) to remove heat released inside the containment vessel following postulated design-basis accident (DBA) such as a loss of coolant accident (LOCA) or a main steam-line break (MSLB).
- W.T. Sha, T.H. Chien, J.G. Sun, B.T. Chao
- 2004
Portions of this doaunent may be illegiile in electronic image products. hags are pm6uced frrwr the best avdiabe original dotmnmt.
- W.T. Sha, T.H. Chien, J.G. Sun, B.T. Chao
- 1997
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What makes AP600 passive safety systems unique?
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What is Rosa AP600?
t, AP600 PASSIVE SYSTEM RELIABILITY ROADMAP! Introduction The AP600 design incorporates passive engineered safety features that perform safety-related functions 1 to mitigate the consequences of design basis accidents and to establish and maintain safe shutdown
Aug 1, 2004 · Analysis of large-scale tests for AP-600 passive containment cooling system. August 2004. Nuclear Engineering and Design 232 (2):197-216. DOI: 10.1016/j.nucengdes.2004.05.003. Authors:...
AP600 and AP1000 are supported by extensive test programs. These programs provided data for code assessment and demonstration of plant & component performance. Nearly all AP600 tests apply to AP1000. Additional tests performed in APEX-AP1000 facility to account for potential deficiencies in supporting database.
Jul 1, 1999 · AP600 passive containment cooling system phenomena identification and ranking table. Full Record. Conference: SAVE / SHARE. Export Metadata. Abstract. This paper presents the Phenomena Identification and Ranking Table (PIRT) used in the containment Design Basis Analysis (DBA) for the AP600 nuclear power plant.
1 I! xiuior.ssnoc<,m issiim c<x u w s m iu nosicsn.sisasussissi,,i,u..s,,si. un u i.ssy,m I,, I! I I I I 1 I AP600 PASSIVE CONTAINMENT COOLING SYSTEM DESIGN BASIS ANALYSIS MODELS, AND MARGIN ASSESSMENT