Effect of RELAP5/MOD3.2 user options on calculated results

被引:0
|
作者
Burtt, JD [1 ]
Shotkin, LM [1 ]
Staudenmeier, JL [1 ]
机构
[1] US NUCL REGULATORY COMMISS,WASHINGTON,DC 20555
关键词
Code calculations; RELAP5; User effect;
D O I
10.13182/NT97-A35401
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Calculations were performed for the same accident scenario in the same power plant geometry using the same version of the RELAP5/MOD3.2 computer code, but each calculation was performed using different user options in the code input deck. The accident scenario analyzed was a 1-in. cold-leg break in the new Westinghouse AP600 design. The calculations were analyzed for those key events leading to actuation of the AP600 automatic depressurization system. Three different user choices for plant system noding were used: (a) a detailed noding with a quasi-three-dimensional vessel; (b) a simplified system noding with a quasi-three-dimensional core, lower plenum, and zipper plenum, bur a simplified downcomer noding; and (c) a detailed system and downcomer noding, but a one-dimensional core, lower plenum, and upper plenum. Two other user options were separately exercised, i.e., shutting off the model for thermal stratification and using different initial temperatures for the core. The discussion focuses on the relative effect of these different user options on flow through the P-loop hot leg, initial reversal inflow through the pressure balance line, timing of draining of the core makeup ranks, and timing of actuation of the automatic depressurization system.
引用
收藏
页码:244 / 268
页数:25
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