Study on step-up characteristic of hydraulic control rod driving system

Nuclear Engineering and Design

Volumn 216, Issue 1-3, 2002, Pages 69-75

  Hanliang, Bo ^a   Yanhua, Zheng ^a   Wenxiang, Zheng ^a   Duo, Dong ^a  

^a TSINGHUA UNIVERSITY   (China)

Author keywords

[No Author keywords available]

Indexed keywords

COOLANTS; HYDRAULIC CONTROL EQUIPMENT; PRESSURE EFFECTS; VALVES (MECHANICAL);

HYDRAULIC CONTROL ROD DRIVING SYSTEMS (HCRDS);

CONTROL RODS;

EID: 0036644508     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0029-5493(02)00030-4     Document Type: Article

References (6)

1. General performance experiment and life test of hydraulic control rod drive system for NHR-200
2. Studies on the performance of the hydraulic control rod drive for NHR-200
3. Preliminary safety analysis report of 200 MW nuclear heating reactor
4. Step dynamic process of the hydraulically-driven control rod, (II) theoretical model on step-down process