Validation of RELAP5/MOD3.2 model on trip off one main coolant pump for VVER 440/V230-Reference-Cited by-同舟云学术

Validation of RELAP5/MOD3.2 model on trip off one main coolant pump for VVER 440/V230

Published:2006-06 Issue:12 Volume:236 Page:1275-1281
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Groudev Pavlin,Stefanova Antoaneta

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference4 articles.

1. Carlson, K.E., et al., 1990. RELAP5/MOD3 Code Manual. User's Guidelines, vol. 1–4, Rev. 1. NUREG/CR-5535, INEL-95/0174.

2. Fletcher, C.D., Schultz, R.R., 1995. RELAP5/MOD3 Code Manual. User's Guidelines, vol. 5, Rev. 1. NUREG/CR-5535, INEL-95/0174.

3. Groudev, P.P., et al., 1999. Engineering Handbook, “Safety Analysis Capability Improvement of KNPP (SACI of KNPP) in the Field of Thermal Hydraulic Analysis”. BOA 278065-A-R4, INRNE-BAS, Sofia, pp. 6–166.

4. Groudev, P.P., et al., 2000. KNPP 440/V230 Transient's Plant data for RELAP5 Model Validation-Part of the Project “Safety Analysis Capability Improvement of KNPP in the Field of Thermal Hydraulic Analysis”. BOA 278065-A-R4, INRNE-BAS, Sofia, pp. 4–41.

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