10.08.2013 Views

Code Manual for CONTAIN 2.0 - Federation of American Scientists

Code Manual for CONTAIN 2.0 - Federation of American Scientists

Code Manual for CONTAIN 2.0 - Federation of American Scientists

SHOW MORE
SHOW LESS

Create successful ePaper yourself

Turn your PDF publications into a flip-book with our unique Google optimized e-Paper software.

Ka192<br />

Kim90<br />

Kro68<br />

Kro78<br />

Lan88a<br />

Lan88b<br />

Lan90<br />

Lei87<br />

Lhi90<br />

Mur83a<br />

H. Karwat, ‘Distribution <strong>of</strong> Hydrogen Within the HDR-Containment Under Severe<br />

Accident Conditions - Final Comparison Report,” OECD Standard Problem OECD- <<br />

CSNI-ISP-29, Organisation <strong>for</strong> Economic Cooperation and Development -<br />

Committee on the Safety <strong>of</strong> Nuclear Installations, August 1992.<br />

M. H. Kim and M. L. Corradini, “Modeling <strong>of</strong> Condensation Heat Transfer in a<br />

Reactor Containment,” Nuclear Engineering and Design, Vol. 118, pp. 193-212,<br />

1990.<br />

D. G. Kroger and W. M. Rohsenow, “Condensation Heat Transfer in the Presence <strong>of</strong><br />

a Noncondensable Gas;’ Int. Journal <strong>of</strong> Heat and Mass Transfer, Vol. 11, pp. 15-26,<br />

1968.<br />

W. J. Krotiuk and M. B. Rubin, “Condensing Heat Transfer Following a Loss-<strong>of</strong>-<br />

Coolant Accident,” Nuclear Technology, Vol. 37, pp. 118-128, 1978.<br />

J. L.anghans, ‘Werifikation der Berechnung von Druckausgleichsstromungen in<br />

<strong>CONTAIN</strong>,” GRS-A-1406, Gesellschaft fur Reaktorsicherheit (GRS) mbH, Koln,<br />

Germany, 1988.<br />

J. Langhans, “<strong>CONTAIN</strong>-Vergleichsrechnung zum HDR-Containment Versuch<br />

T3 1.4,” Report No.73880/GRS-A-1495, Gesellschaft fir Reaktorsicherheit (GRS)<br />

mbH, Koln, Germany, October 1988.<br />

J. Langhans, “Recent Progress in Verification and Development <strong>of</strong> the CONTAJN<br />

<strong>Code</strong>;’ Proceedings <strong>of</strong> the 1990 International Fast Reactor Safety Meeting,<br />

Snowbird, Utah, Vol. 1, p. 279, August 12-16, 1990.<br />

C. D. Leigh, cd., “MELCOR Validation and Verification - 1986 Papers,”<br />

NUREGICR-4830, SAND86-2689, SandiaNationalLaboratories, Albuquerque, NM,<br />

March 1987.<br />

G. Lhiaubet, G. Bunz, M. P. Kissane, H. Seine, O. Miyake, Y. Himeno,<br />

C. Casselman, J. M. Such, and R. Rzekiechi, “Comparison <strong>of</strong> Aerosol Behavior<br />

<strong>Code</strong>s with Experimental Results from a Sodium Fire in a Containment:’<br />

Proceedings <strong>of</strong> the 1990 International Fast Reactor Safety Meeting, Snowbird, UT,<br />

vol. 2, p. 457, August 12-16, 1990.<br />

K. K. Murata, K. D. Bergeron, P. E. Rexroth, M. J. Clauser, J. L. Tills,<br />

F. W. Sciacca, M. E. Senglaub, W. Trebilcock, and D. C. Williams, “<strong>CONTAIN</strong>:<br />

Recent Highlights in <strong>Code</strong> Testing and Validation,” Int. Meeting on Light Water<br />

Reactor Severe Accident Evaluation, Cambridge, MA, August 28-September 1,1983.<br />

Rev. O C-50 6/30/97

Hooray! Your file is uploaded and ready to be published.

Saved successfully!

Ooh no, something went wrong!