-
1
-
-
0041052625
-
ISP no. 28: PHEBUS-SFD B9+ experiment on the degradation of a PWR core type
-
December
-
Adroguer, B., et al., 1992, December. ISP no. 28: PHEBUS-SFD B9+ experiment on the degradation of a PWR core type. Comparison report, OECD/NEA/CSNI/R (92) 17.
-
(1992)
Comparison Report
, vol.OECD-NEA-CSNI-R
, Issue.92
, pp. 17
-
-
Adroguer, B.1
-
4
-
-
0026253758
-
Simulation with the HITO code of the interaction of zircaloy with uranium dioxide and steam at high temperatures
-
Denis A., Garcia E. Simulation with the HITO code of the interaction of zircaloy with uranium dioxide and steam at high temperatures. J. Nucl. Mater. 185:1991;96-113.
-
(1991)
J. Nucl. Mater.
, vol.185
, pp. 96-113
-
-
Denis, A.1
Garcia, E.2
-
5
-
-
3242671140
-
ICARE/CATHARE: A computer code for analysis of severe accidents in LWRs, ICARE2 V3mod1: Description of physical models
-
July
-
Fichot, F., et al., 2001, July. ICARE/CATHARE: a computer code for analysis of severe accidents in LWRs, ICARE2 V3mod1: description of physical models. Technical note DRS/SEMAR 00/03.
-
(2001)
Technical Note
, vol.DRS-SEMAR 00-03
-
-
Fichot, F.1
-
8
-
-
3242724607
-
Experimental and theoretical results of cladding oxidation under severe fuel-damage conditions
-
Adamson, R.B., Van Swan, L.F.P (Eds.), ASTM STP 939. American Society for Testing and Materials, Philadelphia
-
Hofmann, P., Neitzel, H.J., 1987. Experimental and theoretical results of cladding oxidation under severe fuel-damage conditions. In: Adamson, R.B., Van Swan, L.F.P (Eds.), Zirconium in the Nuclear Industry: 7th International Symposium, ASTM STP 939. American Society for Testing and Materials, Philadelphia, pp. 504-538.
-
(1987)
Zirconium in the Nuclear Industry: 7th International Symposium
, pp. 504-538
-
-
Hofmann, P.1
Neitzel, H.J.2
-
9
-
-
3242720978
-
-
October. Unpublished information given at Proceedings from the ICARE2 Users' Club Second Seminar, Aix-en-Provence
-
Kobzar, V., Yegorova, L., Zvonarev, Yu., 1996, October. An approach to estimate SFD codes quality and demonstration of application to the ICARE2 V2 Mod2.1 code and PHEBUS B9+ test results. Unpublished information given at Proceedings from the ICARE2 Users' Club Second Seminar, Aix-en-Provence.
-
(1996)
An Approach to Estimate SFD Codes Quality and Demonstration of Application to the ICARE2 V2 Mod2.1 Code and PHEBUS B9+ Test Results
-
-
Kobzar, V.1
Yegorova, L.2
Zvonarev, Yu.3
-
10
-
-
0022767405
-
Oxidation kinetics and related phenomena of zircaloy-4 fuel cladding exposed to high temperature steam and hydrogen-steam mixtures under PWR accident conditions
-
Leistikow S., Schanz G. Oxidation kinetics and related phenomena of zircaloy-4 fuel cladding exposed to high temperature steam and hydrogen-steam mixtures under PWR accident conditions. Nucl. Eng. Des. 103:1987;65-84.
-
(1987)
Nucl. Eng. Des.
, vol.103
, pp. 65-84
-
-
Leistikow, S.1
Schanz, G.2
-
11
-
-
0018490980
-
Oxygen diffusion in the oxide and alpha phases during reaction of zircaloy-4 with steam from 1000 °C to 1500 °C
-
Pawel R.E. Oxygen diffusion in the oxide and alpha phases during reaction of zircaloy-4 with steam from 1000 °C to 1500 °C. J. Electrochem. Soc. 126(7):1979;1111-1118.
-
(1979)
J. Electrochem. Soc.
, vol.126
, Issue.7
, pp. 1111-1118
-
-
Pawel, R.E.1
-
12
-
-
84916145771
-
Oxidation of zircaloy-4 in steam at 1300 °C to 2400 °C
-
Adamson, R.B., Van Swan, L.F.P. (Eds.), ASTM STP 939. American Society for Testing and Materials, Philadelphia
-
Prater, J.T., Courtright, E.L., 1987. Oxidation of zircaloy-4 in steam at 1300 °C to 2400 °C. In: Adamson, R.B., Van Swan, L.F.P. (Eds.), Zirconium in the Nuclear Industry: 7th International Symposium, ASTM STP 939. American Society for Testing and Materials, Philadelphia, pp. 489-503.
-
(1987)
Zirconium in the Nuclear Industry: 7th International Symposium
, pp. 489-503
-
-
Prater, J.T.1
Courtright, E.L.2
-
13
-
-
3242677986
-
Advanced treatment of zircaloy cladding high-temperature oxidation in severe accident code calculations. Part I. Experimental database and basic modeling
-
Schanz, G., Adroguer, B., Volchek, A., 2004. Advanced treatment of zircaloy cladding high-temperature oxidation in severe accident code calculations. Part I. Experimental database and basic modeling. Nucl. Eng. Des. 232, 75-84.
-
(2004)
Nucl. Eng. Des.
, vol.232
, pp. 75-84
-
-
Schanz, G.1
Adroguer, B.2
Volchek, A.3
-
14
-
-
0018005287
-
High-temperature oxidation of zircaloy-2 and zircaloy-4 in steam
-
Urbanic V.F., Heidrick T.R. High-temperature oxidation of zircaloy-2 and zircaloy-4 in steam. J. Nucl. Mater. 75:1978;251-261.
-
(1978)
J. Nucl. Mater.
, vol.75
, pp. 251-261
-
-
Urbanic, V.F.1
Heidrick, T.R.2
-
15
-
-
3242660013
-
Advanced treatment of zircaloy cladding high-temperature oxidation in severe accident code calculations. Part II. Best-fitted parabolic correlations
-
Volchek, A., Zvonarev, Yu., Schanz, G., 2004. Advanced treatment of zircaloy cladding high-temperature oxidation in severe accident code calculations. Part II. Best-fitted parabolic correlations. Nucl. Eng. Des. 232, 85-96.
-
(2004)
Nucl. Eng. Des.
, vol.232
, pp. 85-96
-
-
Volchek, A.1
Zvonarev, Yu.2
Schanz, G.3
|