Review of the materials-chemistry models in the VICTORIA code
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OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Radioactive element chemistry and processing
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References (32)
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1. US Nuclear Regulatory Commission, “Reassessment of the Technical Bases for Estimating Source Terms,” NUREG-0956, Washington, DC, 1986
2. J.A. Gieseke et al., Source Term Code Package, NUREG/CR-4587, Battelle Columbus Laboratories, 1986
3. US Nuclear Regulatory Commission, Nuclear Power Plant Severe Accident Research Plan. NUREG-0900, Rev. 1, 1986.
4. T.J. Heames et al., VICTORIA Code Manual, NUREG/CR-5545, Rev. 1, Sandia National Laboratories, 1992
5. B.E. Boyack, V.K. Dhir, J.A. Gieseke, T.J. Haste, M.A. Kenton, M. Khatib-Rahbar, M.T. Leonard, R. Viskanta, MELCOR Peer Review, Los Alamos National Laboratory Report LA-12240, March 199210.2172/10139479 ↗
6. Boyack, B.E., M.L. Corradini, R.S. Denning, M. Khatib-Rahbar, S.K. Loyalka, P.N. Smith, CONTAIN Independent Peer Review, Los Alamos National Laboratory Report LA-12866, January 199510.2172/10115334 ↗
7. Corradini, M.L., V.K. Dhir, T.J. Haste, T.J. Heames, R.P. Jenks, J.E. Kelly, M. Khatib-Rahbar, R. Viskanta, SCDAP/RELAP5 Independent Peer Review, Los Alamos National Laboratory Report LA-12481, January 199310.2172/10147242 ↗
8. Mubayi, V., J.A. Gieseke, D.R. Olander, M. Schwarz, VICTORIA Independent Peer Review, Brookhaven National Laboratory, Technical Report W-6436, April 1997
9. Ball, R.G.J., R.A. Barton, M.A. Mignanelli, Assessment of the Thermodynamic Database in the VICTORIA Code, AEA Thermal Reactor Services, AEA-TRS-2048, AEA Technology, Harwell, UK, January 199110.1016/0963-8695(91)90808-G ↗
10. I. Ansara, B. Sundman, SGTE, Scientific Group Thermodata Europe, in: P.S. Glaeser (Ed.), Computer Handling and Dissemination of Data, Elsevier, Amsterdam, 1987, p. 154
11. V.P. Glushko et al., IVTAN, Termodinamicheskie Svoistva Individual `nykh Veshchestv, Tom. IV, Nauka, Moscow [no date].
12. E.H.P. Cordfunke et al., Thermochemical Data for Reactor Materials and Fission Products, Elsevier, Amsterdam, 199010.1016/0022-3115(89)90443-1 ↗
13. I. Barin, Thermochemical Data of Pure Substances: Part I and II, VCH, Weinheim, Germany, 1989
14. K.C. Mills, Thermodynamic Data for Inorganic Sulphides, Selenides, Tellurides, Butterworth, London, 1974
15. D. Lamy et al., Modeling the Chemical Behavior of Tellurium Species in the Reactor Pressure Vessel and the Reactor Coolant System under Severe Accident Conditions, SCK/CEN Report No. R2778, 1990
16. W.T. Thompson, M.H. Kaye, memo to B.J. Lewis (unpublished)
17. W.T. Thompson, M.H. Kaye, An Examination of the Europium Hydroxide Data from the VICTORIA Code (unpublished)
18. Cubiocciotti · J. Nucl. Mater. · 1988 · 154 · 5310.1016/0022-3115(88)90118-3 ↗
19. D.I. Chanin, H.N. Jow, J.A. Rollstin, MELCOR Accident Consequence System (MACCS), Sandia National Laboratories, NUREG/CR-4691, 199010.2172/7172209 ↗
20. Wang · J. Nucl. Mater. · 1994 · 211 · 8510.1016/0022-3115(94)90283-6 ↗
21. Grimes · Philos. Trans. Royal Soc. Land. A · 1991 · 335 · 60910.1098/rsta.1991.0062 ↗
22. V. Ozrin et al., Models for Release of Low-Volatile Fission Products, Nuclear Safety Institute of the RussianAcademy of Sciences, NSI-SARR-43-96, 1996
23. D.R. Olander, these Proceedings, p. 187
24. Blackburn · J. Nucl. Mater. · 1973 · 46 · 24410.1016/0022-3115(73)90038-X ↗
25. Lindemer · J. Nucl. Mater. · 1985 · 130 · 47310.1016/0022-3115(85)90334-4 ↗
26. S.G. Prussin et al., Release of Volatile Fission Products from UO2, Proc. Amer. Nucl. Soc. Topical Mtg. on Fission Product Behavior and Source Term Research, EPRI Report NP-4113-SR, 1985
27. Urbanic · J. Nucl. Mater. · 1978 · 75 · 25110.1016/0022-3115(78)90006-5 ↗
28. Ott · Trans. Am. Nucl. Soc. · 1997 · 77 · 422
29. Olander · Nucl. Eng. Design · 1994 · 148 · 27310.1016/0029-5493(94)90114-7 ↗
30. M. Firnhaber et al., International Standard Problem 31, CORA-13 Experiment on Severe Fuel Damage, Preliminary Comparison Report, presented at the ISP 31 Workshop, FZK, Karlsruhe, Germany, August 1992
31. A. Bejan, Convection Heat Transfer, Wiley, New York, 1984, pp. 89–91
32. Olander · Nucl. Eng. Design · 1994 · 148 · 25310.1016/0029-5493(94)90113-9 ↗