scholarly journals SCORE-EVET: a computer code for the multidimensional transient thermal-hydraulic analysis of nuclear fuel rod arrays. [BWR; PWR]

1978 ◽  
Author(s):  
R. L. Benedetti ◽  
L. V. Lords ◽  
D. M. Kiser
2016 ◽  
pp. 9-12
Author(s):  
Yu. Vorobyov ◽  
A. Nosovsky ◽  
O. Pohonets ◽  
I. Shevchenko

The paper presents thermal-hydraulic analysis of mixed core loads to confirm compliance with safety criteria. The objective is to verify reliability of nuclear fuel cooling in representative events of the design-basis accident analysis. RELAP5/MOD3.2 computer code was applied to show that maximum fuel cladding temperature does not exceed 1200 °C in mixed TVSA-12, TVS-WR and TVSA cores. The analysis led to the conclusion on possible safe implementation of new fuel at Ukrainian NPPs.


2018 ◽  
Vol 204 (1) ◽  
pp. 15-24 ◽  
Author(s):  
Yuchuan Guo ◽  
Guanbo Wang ◽  
Dazhi Qian ◽  
Heng Yu ◽  
Bo Hu ◽  
...  

2013 ◽  
Vol 62 ◽  
pp. 144-152 ◽  
Author(s):  
Omar S. AL-Yahia ◽  
Mohammad A. Albati ◽  
Jonghark Park ◽  
Heetaek Chae ◽  
Daeseong Jo

2014 ◽  
Vol 71 ◽  
pp. 152-159 ◽  
Author(s):  
Hao Zhao ◽  
Dahuan Zhu ◽  
Khurrum Saleem Chaudri ◽  
Suizheng Qiu ◽  
Wenxi Tian ◽  
...  

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