Thermal reactor safety assessment
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43

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

Thermal reactor safety assessment ◽

10.1680/trsa.19935.0014 ◽

1994 ◽

pp. 83-87

Author(s):

J. L. Wilson ◽

J. A. Burrows

Keyword(s):

Safety Analysis ◽

Thermal Reactor ◽

Reactor Safety ◽

Code Validation

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32. CEC reinforced concerted action on source term

Thermal reactor safety assessment ◽

10.1680/trsa.19935.0032 ◽

1994 ◽

pp. 194-199

Author(s):

W. Balz ◽

B. R. Bowsher

Keyword(s):

Source Term ◽

Concerted Action

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35. A new approach to graphite core safety cases

Thermal reactor safety assessment ◽

10.1680/trsa.19935.0036 ◽

1994 ◽

pp. 219-223

Author(s):

N. McLachlan ◽

D. Dicks ◽

M. O. Tucker

Keyword(s):

New Approach ◽

Safety Cases

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29. The use of the core reliability model as a multiple repairable system in analytical-statistical simulation for RMBK PRA

Thermal reactor safety assessment ◽

10.1680/trsa.19935.0030 ◽

1994 ◽

pp. 180-186

Author(s):

R. T. Islamov

Keyword(s):

Statistical Simulation ◽

Repairable System ◽

Reliability Model ◽

The Core

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37. The Sizewell B Level 2 PSA Analysis

Thermal reactor safety assessment ◽

10.1680/trsa.19935.0038 ◽

1994 ◽

pp. 232-239

Author(s):

M. L. Ang ◽

N. E. Buttery ◽

S. H. M. Jones ◽

D. B. Utton

Keyword(s):

Level 2

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3. AC/DC power supply system fault tree analysis

Thermal reactor safety assessment ◽

10.1680/trsa.19935.0003 ◽

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

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14. Results of the Sizewell B probabilistic safety analysis

Thermal reactor safety assessment ◽

10.1680/trsa.19935.0017 ◽

1994 ◽

pp. 100-107

Author(s):

P. J. Ross ◽

C. Dawson

Keyword(s):

Safety Analysis ◽

Probabilistic Safety

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7. An SGTR and SB LOCA analysis for Krsko NPP

Thermal reactor safety assessment ◽

10.1680/trsa.19935.0008 ◽

1994 ◽

pp. 46-52

Author(s):

S. Petelin ◽

I. Parzer ◽

A. Prosek ◽

B. Mavko

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40. Three Mile Island reactor vessel investigation and findings

Thermal reactor safety assessment ◽

10.1680/trsa.19935.0040 ◽

1994 ◽

pp. 246-253

Author(s):

E. Beckjord ◽

A. Rubin

Keyword(s):

Reactor Vessel

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

Thermal reactor safety assessment ◽

10.1680/trsa.19935.0041 ◽

1994 ◽

pp. 254-259

Author(s):

B. A. Coxson

Keyword(s):

Reliability Data

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