Thermal reactor safety assessment
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Published By Thomas Telford Publishing

0727752642
Latest Documents Most Cited Documents Contributed Authors Related Sources Related Keywords

12. The role of code validation in thermal reactor safety analysis

1994 ◽  
pp. 83-87
Author(s):  
J. L. Wilson ◽  
J. A. Burrows
Keyword(s):  
Safety Analysis ◽  
Thermal Reactor ◽  
Reactor Safety ◽  
Code Validation

32. CEC reinforced concerted action on source term

1994 ◽  
pp. 194-199
Author(s):  
W. Balz ◽  
B. R. Bowsher
Keyword(s):  
Source Term ◽  
Concerted Action

35. A new approach to graphite core safety cases

1994 ◽  
pp. 219-223
Author(s):  
N. McLachlan ◽  
D. Dicks ◽  
M. O. Tucker
Keyword(s):  
New Approach ◽  
Safety Cases

37. The Sizewell B Level 2 PSA Analysis

1994 ◽  
pp. 232-239
Author(s):  
M. L. Ang ◽  
N. E. Buttery ◽  
S. H. M. Jones ◽  
D. B. Utton
Keyword(s):  
Level 2

3. AC/DC power supply system fault tree analysis

1994 ◽  
pp. 13-17
Author(s):  
M. Cepin ◽  
R. Jordan ◽  
M. Kozuh
Keyword(s):  
Power Supply ◽  
Power Supply System ◽  
Fault Tree ◽  
Fault Tree Analysis ◽  
Supply System ◽  
Tree Analysis ◽  
Dc Power ◽  
Dc Power Supply

14. Results of the Sizewell B probabilistic safety analysis

1994 ◽  
pp. 100-107
Author(s):  
P. J. Ross ◽  
C. Dawson
Keyword(s):  
Safety Analysis ◽  
Probabilistic Safety

7. An SGTR and SB LOCA analysis for Krsko NPP

1994 ◽  
pp. 46-52
Author(s):  
S. Petelin ◽  
I. Parzer ◽  
A. Prosek ◽  
B. Mavko

40. Three Mile Island reactor vessel investigation and findings

1994 ◽  
pp. 246-253
Author(s):  
E. Beckjord ◽  
A. Rubin
Keyword(s):  
Reactor Vessel

41. The derivation of operational and reliability data for the Sizewell B PSA

1994 ◽  
pp. 254-259
Author(s):  
B. A. Coxson
Keyword(s):  
Reliability Data
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