-
1
-
-
0346332422
-
Code qualification document for best-estimate LOCA analysis
-
S.M. Bajorek, "Code Qualification Document for Best-Estimate LOCA Analysis" WCAP-12945 (1992).
-
(1992)
WCAP-12945
-
-
Bajorek, S.M.1
-
2
-
-
0010695798
-
COBRA/TRAC - A thermal-hydraulics code for transient analysis of nuclear reactor vessels and primary coolant systems
-
M. J. Thurgood et al, "COBRA/TRAC - A Thermal-Hydraulics Code for Transient Analysis of Nuclear Reactor Vessels and Primary Coolant Systems," NUREG/CR-3046 (1983)
-
(1983)
NUREG/CR-3046
-
-
Thurgood, M.J.1
-
4
-
-
0343059282
-
TRAC-PD2, an advanced best-estimate computer program for pressurized water reactor loss-of-coolant accident analysis
-
D.R. Liles et al., "TRAC-PD2, An Advanced Best-Estimate Computer Program for Pressurized Water Reactor Loss-of-Coolant Accident Analysis," NUREG/CR-2054. (1981)
-
(1981)
NUREG/CR-2054
-
-
Liles, D.R.1
-
5
-
-
84880457436
-
Analysis of FLECHT-SEASET 163 rod bundle data using COBRA-TF
-
C.Y. Paik and L.E. Hochreiter, "Analysis of FLECHT-SEASET 163 Rod Bundle Data Using COBRA-TF," NUREG/CR-4166 (1986).
-
(1986)
NUREG/CR-4166
-
-
Paik, C.Y.1
Hochreiter, L.E.2
-
6
-
-
0012482956
-
Quantifying reactor safety margins: Application of code scaling, applicability, and uncertainty evaluation methodology to large break, loss-of-coolant accident
-
B. Boyack et al., "Quantifying Reactor Safety Margins: Application of Code Scaling, Applicability, and Uncertainty Evaluation Methodology to Large Break, Loss-of-Coolant Accident," NUREG/CR-5249. (1989).
-
(1989)
NUREG/CR-5249
-
-
Boyack, B.1
-
7
-
-
84907080754
-
Findings on user effect of IAEA international standard problem exercise no, 4
-
Washington, D.C., USA
-
M. Mavko and A. Prosek, "Findings on user effect of IAEA international standard problem exercise No, 4," Proc. Of the Internationa Meeting on Best-Estimate Methods in Nuclear Installation Safety Analysis (BE-2000), Washington, D.C., USA (2000)
-
(2000)
Proc. of the Internationa Meeting on Best-Estimate Methods in Nuclear Installation Safety Analysis (BE-2000)
-
-
Mavko, M.1
Prosek, A.2
-
8
-
-
0343345570
-
User effects on the thermal-hydraulic transient system code calculations
-
S. N. Aksan, F. D'Auria and H. Stadtke, "User effects on the thermal-hydraulic transient system code calculations," Nucl. Engineering and Design, 145, 159-174 (1993).
-
(1993)
Nucl. Engineering and Design
, vol.145
, pp. 159-174
-
-
Aksan, S.N.1
D'Auria, F.2
Stadtke, H.3
-
10
-
-
0032206536
-
Application of the WCOBRA/TRAC best-estimate methodology to the AP600 large-break LOCA analysis
-
J. Zhang, S. M. Bajorek, R. M. Kemper, M. E. Nissley, N. Petkov, and L. E. Hochreiter, "Application of the WCOBRA/TRAC best-estimate methodology to the AP600 large-break LOCA analysis," Nuclear Engineering and Design, Vol. 186 (1998), Nos. 1-2, pg. 279-301.
-
(1998)
Nuclear Engineering and Design
, vol.186
, Issue.1-2
, pp. 279-301
-
-
Zhang, J.1
Bajorek, S.M.2
Kemper, R.M.3
Nissley, M.E.4
Petkov, N.5
Hochreiter, L.E.6
-
12
-
-
0346307940
-
Assessment of flooding in a best-estimate thermal hydraulic code (WCOBRA/TRAC)
-
K. Takeuchi, and M. Y. Young, "Assessment of flooding in a best-estimate thermal hydraulic code (WCOBRA/TRAC)," Nuclear Engineering and Design, Vol. 186 (1998), Nos. 1-2, pg. 225-255.
-
(1998)
Nuclear Engineering and Design
, vol.186
, Issue.1-2
, pp. 225-255
-
-
Takeuchi, K.1
Young, M.Y.2
-
13
-
-
0347568942
-
Scaling effects predicted by WCOBRA/TRAC for UPI plant best estimate LOCA
-
K. Takeuchi, M. E. Nissley, J. S. Spaargaren, and S. I. Dederer, "Scaling effects predicted by WCOBRA/TRAC for UPI plant best estimate LOCA," Nuclear Engineering and Design, Vol. 186 (1998), Nos. 1-2, pg. 257-278.
-
(1998)
Nuclear Engineering and Design
, vol.186
, Issue.1-2
, pp. 257-278
-
-
Takeuchi, K.1
Nissley, M.E.2
Spaargaren, J.S.3
Dederer, S.I.4
|