Code Manual for CONTAIN 2.0 - Federation of American Scientists

Ti191
Ti196
Uch65
Va183
va188
Ver87
wan88
was88
Wie88
Wi187
J. Tills, V. Nicolette, and K. Washington, “Initial Performance Assessment of the
Westinghouse AP600 Containment Design and Related Safety Issues;’ NUREG/CP-
0118, Proceedings of the U. S. Nuclear Regulatory Commission Nineteenth Water
Reactor Safety Znformution Meeting, Bethesda, MD, October 28-30, 1991.
J. Tills, ‘Calculations and Analysis for the Large-Scale Passive Containment Cooling
System (PCS) Tests,” SAND96-1089 (Proprietary), Sandia National Laboratories,
Albuquerque, NM, May 1996.
H. Uchid4 A. Oyama, and Y. Togo, “Evaluation of Post-Incident Cooling Systems
of Light-Water Power Reactors,” Proceedings of the Z%irdInternational Conference
on the Peacefid Uses of Atomic Energy, Genev~ August 31-September 9, 1964, Vol.
13, pp. 93-104, United Nations, New York, 1965.
L. Valencia and T. F. Kanzleiter, “Blowdown-Investigations in a Reactor
Containment -- Rupture of a Steam Pipe -- Quick Look Report for Tests V42, V43,
and V44,” Technical Report PHDR 38-83, Forschungszentrurn, Karlsruhe, Germany,
May 1983.
G. D. Valdez, “Review and Implementation of Thermodynamic and Transport
Properties for the CONTAIN Code,” NUREG/CR-5 173, SAND88-7 101, Sandia
National Laboratories, Albuquerque, NM, November 1988.
P. J. Vernier and P. Solignac, “A Test of Some Condensation Models in the Presence
of a Noncondensable Gas Against the ECOTRA Experiment,” Nuclear Technology,
Vol. 77, pp. 82-91, 1987.
C. Wang and C. Tu, “Effects of Non-Condensable Gas on Laminar Film
Condensation in a Vertical Tube:’ Int. Journal of Heat and Mass Transfer, Vol.31,
No. 11, pp. 2339-2345, 1988.
K. E. Washington and D. E. Carroll, “Assessment of Models for Steam Release from
Concrete and Implications for Modeling Corium Behavior in Reactor Cavities,”
SAND88-2329C, Sixteenth Water Reactor Safety Information Meeting,
Gaithersburg, MD, October 24-27, 1988.
J. Wiesemes, “CONTAIN-Rechnungen zum Aerosol Verhalten fur Fall 7 Der SNR-
Risikostudie,” (in German), GRS-A-1488, Gesellschaft fur Reaktorsicherheit (GRS)
mbH, Koln, Germany, October 1988.
D. C. Williams et al., “Containment Loads Due to Direct Containment Heating and
Associated Hydrogen Behavior: Analysis and Calculations with the CONTAIN
Code,” NUREG/CR-4896, SAND87-0633, Sandia National Laboratories,
Albuquerque, NM, May 1987.
Rev O c-53 6/30/97