-
1
-
-
0028197894
-
Risk assessment for dynamic systems: An overview
-
Siu, N., Risk assessment for dynamic systems: an overview. Reliab. Engng System Safety, 43 (1994) 43-73.
-
(1994)
Reliab. Engng System Safety
, vol.43
, pp. 43-73
-
-
Siu, N.1
-
2
-
-
0024134757
-
Accident sequence dynamic simulation vs event trees
-
Amendola, A., Accident sequence dynamic simulation vs event trees. Reliab. Engng System Safety, 22 (1988).
-
(1988)
Reliab. Engng System Safety
, vol.22
-
-
Amendola, A.1
-
3
-
-
0041968770
-
Dynamic event tree analysis method (DETAM) for accident sequence analysis
-
prepared for US Nuclear Regulatory Commission
-
Acosta, C. G. & Siu, N., Dynamic event tree analysis method (DETAM) for accident sequence analysis. NUREG/CR-5608, prepared for US Nuclear Regulatory Commission, 1992.
-
(1992)
NUREG/CR-5608
-
-
Acosta, C.G.1
Siu, N.2
-
4
-
-
0041467593
-
Dynamic accident sequence simulator for probabilistic safety assessment
-
1993, Florida, 26-29 January
-
Hsueh, K. S. & Mosleh, A., Dynamic accident sequence simulator for probabilistic safety assessment. In 1993 PSA Int. Topical Meeting, Florida, 26-29 January 1993.
-
(1993)
PSA Int. Topical Meeting
-
-
Hsueh, K.S.1
Mosleh, A.2
-
5
-
-
0026884986
-
Probabilistic reactor dynamics-I: The theory of continuous event trees
-
Devooght, J. & Smidts, C., Probabilistic reactor dynamics-I: the theory of continuous event trees. Nucl. Sci. Engng, 111 (1992) 229-240.
-
(1992)
Nucl. Sci. Engng
, vol.111
, pp. 229-240
-
-
Devooght, J.1
Smidts, C.2
-
6
-
-
0041968769
-
MSAS: Description and how-to-use commission of the European Communities
-
ISPRA, Italy
-
Smidts, C., MSAS: description and how-to-use commission of the European Communities. Technical reports ISEI/SER 2318/92, ISPRA, Italy, 1992.
-
(1992)
Technical Reports ISEI/SER 2318/92
-
-
Smidts, C.1
-
7
-
-
0010735276
-
-
US Nuclear Regulator Commission, NUREG/CR-4312, EGG-2396
-
Ransom, V. H. et al., RELAP/MOD2 Code Manual, US Nuclear Regulator Commission, NUREG/CR-4312, EGG-2396, 1985.
-
(1985)
RELAP/MOD2 Code Manual
-
-
Ransom, V.H.1
-
8
-
-
0041467580
-
RETRANS-02: A program for transient thermal-hydraulic analysis of complex fluid flow systems
-
Paulsen, M. P., et al., RETRANS-02: a program for transient thermal-hydraulic analysis of complex fluid flow systems. ERPI NP-1850-CCM, 1984.
-
(1984)
ERPI NP-1850-CCM
-
-
Paulsen, M.P.1
-
9
-
-
85029974726
-
Categorization of operator errors in the context of symptom-based emergency operating procedures
-
Tokyo, August
-
Hsueh, K. S. & Mosleh, A., Categorization of operator errors in the context of symptom-based emergency operating procedures. In SMiRT, Tokyo, August, 1991.
-
(1991)
SMiRT
-
-
Hsueh, K.S.1
Mosleh, A.2
-
10
-
-
0041467579
-
Hydrodynamic models for the treatment of reactor thermal transients
-
Meyer, J.E. Hydrodynamic models for the treatment of reactor thermal transients. Nucl. Sci. Engng, 19 (1961).
-
(1961)
Nucl. Sci. Engng
, vol.19
-
-
Meyer, J.E.1
-
11
-
-
0004109341
-
-
Hemisphere Publishing Corporation, New York
-
Todreas, N. & Kazimi, M., Nuclear System, Hemisphere Publishing Corporation, New York, 1990.
-
(1990)
Nuclear System
-
-
Todreas, N.1
Kazimi, M.2
-
12
-
-
33748145541
-
Seabrook simulator model upgrade: Implementation and validation of two-phase, nonequilibrium RCS and steam generator models
-
EPRI GS/NP-6670
-
Kao, K., Seabrook simulator model upgrade: implementation and validation of two-phase, nonequilibrium RCS and steam generator models. In Proc. Conf. Power Plant Simulators and Modelling, EPRI GS/NP-6670, 1988.
-
(1988)
Proc. Conf. Power Plant Simulators and Modelling
-
-
Kao, K.1
-
13
-
-
0042970464
-
-
PLG-0300, prepared for Public Service Company of New Hampshire and Yankee Atomic Electric Company by Pickard Lowe and Garrick, Inc., California
-
Seabrook station probabilistic safety assessment. PLG-0300, prepared for Public Service Company of New Hampshire and Yankee Atomic Electric Company by Pickard Lowe and Garrick, Inc., California, 1983.
-
(1983)
Seabrook Station Probabilistic Safety Assessment
-
-
|