1 |
T.G. Theofanous, W.W. Yuen, S. Angelini, J.J. Sienicki, K. Freeman, X. Chen and T. Salmassi, 'Lower head integrity under in-vessel steam explosion loads', DOE/ID-10541 U.S. Department of Energy Report (1996)
|
2 |
SERG2, 'A reassessment of the potential for an Alpha-Mode containment failure and a review of the broader fuel coolant interaction (FCI) issues', NUREG-1529, U.S. NRC Report (1995)
|
3 |
M.M. Pilch et al., 'The probability of containment failure by direct containment heating in Zion', NUREG/CR-6075, U.S. NRC Report (1993)
|
4 |
J.Q. Howieson and V.G. Snell 'Chernobyl - A Canadian Technical Perspective', Nuclear Journal of Canada, No 3 (Sepember 1987)
|
5 |
A technical executive summary of this is in: V.G. Snell and J.Q. Howieson 'Chernobyl ? A Canadian Technical Perspective - Executive summary', Atomic Energy of Canada Ltd publication AECL-9334S, (January 1987)
|
6 |
B.R. Sehgal, 'Accomplishments and Challenges of the Severe Accident Research', Nucl. Eng. Design, 210, 79 (2001)
DOI
ScienceOn
|
7 |
Electric Power Research Institute (EPRI), 'MAAP 4, Modular Accident Analysis Program User's Manual', EPRI Report prepared by Fauske & Associates Inc. (1994)
|
8 |
F.R. Farmer, 'Siting Criteria-A New Approach', Proceedings of a Symposium on Containment and Siting, International Atomic Agency, Vienna (1967)
|
9 |
U.S. Nuclear Regulatory Commission, 'Reactor Safety Study. An Assessment of Accident Risks in .U.S. Commercial Nuclear Power Plants', USAEC Report, WASH-1400 (1975)
|
10 |
H.W. Lewis et al., 'Risk Assessment Review Group Report to the U.S. Nuclear Regulatory Commission', U.S. NRC Report NUREG/CR-0400, U.S. Nuclear Regulatory Commission (1978)
|
11 |
Federal Minister for Research and Technology, 'The German Risk Study: Nuclear Power Plants', Verlag TUV Rheinland, (1980) (In German)
|
12 |
Report of the President's Commission on the Accident on Three Mile Island, Washington D.C. (1979)
|
13 |
D. Cubicciotti and B.R. Sehgal, 'Vapor Transport of Fission Products in Postulated Severe Light Water Reactor Accidents', Nucl. Technology 65, 266 (May 1984)
DOI
|
14 |
U.S. Atomic Energy Commission, 'Emergency Core Cooling, Report of an Advisory Task Force', USAEC Report TID-24226 (Jan. 1968)
|
15 |
Report to the American Physical Society of The Study Group on Light-Water Reactor Safety Rev.Mod.Phys, Vol 47, Suppl No.1, (1975)
DOI
|
16 |
U.S. Atomic Energy Commission, 'General Design Criteria for Nuclear Power Plants', Code of Federal Register, 10 CFR 50 Appendix A, (1971)
|
17 |
W.B. Cottrell, 'The ECCS Rule-Making Hearings', Nucl. Safety, Vol 15, No 1 (1974)
|
18 |
U.S. Atomic Energy Commission, 'Theoretical Possibilities and Consequences of Major Accidents in Large Nuclear Power Plants', USAEC Report WASH-740, (March 1957)
|
19 |
United States Atomic Energy Commission Report 'Siting Criteria', TID14844 USAEC Report (1959)
|
20 |
D. Okrent, Nuclear Reactor Safety, On the History of the Regulating Process, University of Wisconsin Press (1981)
|
21 |
U.S. Atomic Energy Commission, 'The Safety of Nuclear Power Reactors (Light Water Cooled ) and Related Facilities', USAEC Report WASH-1250 (July 1973)
|
22 |
J.M. Seiler, B.R. Sehgal et al., 'European Group for analysis of corium concepts' Proceedings of the FISA Conference, European Commission (2003)
|
23 |
J.R. Dietrich, 'Experimental Determination of the Self-Regulation and Safety of Operating Water -Moderated Reactors', Proceedings of the International Conference on the Peaceful Uses of Atomic Energy, United Nations, New York, 1956
|
24 |
H.M. Parker and J.W. Healy, 'Environmental Effects of a Major Reactor Disaster', Proceedings of the International Conference on the Peaceful Uses of Atomic Energy, United Nations, New York, (1956)
|
25 |
S. Glasstone, Sourcebook on Atomic Energy, 3rd Edition, D van Nostrand Company Inc (1967)
|
26 |
T.J. Thompson and J.G. Beckerley, The Technology of Nuclear Power Reactor Safety, Vol.1, The MIT Press, (1970)
|
27 |
A.M. Weinberg, 'A Second Era, Prospects and Perspectives', Presented at the 40th Anniversary of the First Nuclear Chain Reactor, University of Chicago, 1-2 December, (1982)
|
28 |
T.N. Dinh, M.J. Konovalikhin and B.R. Sehgal, 'Core melt spreading on a reactor containment floor', Progress in Nuclear Energy 36, No.4, Pergamon Press (2000)
DOI
ScienceOn
|
29 |
J.K. Fink, D.H. Thompson, D.R. Armstrong, B.W. Spencer and B.R. Sehgal. 'Aerosol and Melt Chemistry in ACE molten corium concrete interaction experiments', High Temperature Science, (1994)
|
30 |
NEA/OECD Report, 'Implementing severe accident management in nuclear power plants', SESAM Group, NEA/OECD (1996)
|
31 |
A.K. Nayak, B.R. Sehgal and A.V. Stepanyan, 'An experimental study on quenching of a radially-stratified heated porous bed', Nucl. Eng. Design 236, 2189 (2006)
DOI
ScienceOn
|
32 |
V.V. Asmolov, 'Last findings of the RASPLAV Project', Proceedings OECD/CSNI workshop on in-vessel core debris retention and coolability, Munich OECD/NEA Report (1999)
|
33 |
V.V. Asmolov et. al., 'Zirconium and Uranium partitioning between oxide and metallic phases of molten corium', MPTR-9, RRC Kurchatov Institute Russia (2003)
|
34 |
M. Fischer, O. Herbst and H. Schmidt, 'Demonstration of the heat removing capabilities of the EPR core catcher', Nucl. Eng. Design 235, 1189 (2005)
DOI
ScienceOn
|
35 |
M.T. Farmer, S. Lomperski and S. Basu, 'The results of the CCI-3 reactor material experiments investigating 2-D core-concrete interaction and debris coolability with a siliceous concrete crucible', Proceedings of the ICAPP'06, Reno U.S. (June 4-8, 2006)
|
36 |
M.J. Konovalikhin, A. Karbojian and B.R. Sehgal, 'Molten pool coolability. COMECO Experiments', Proceedings of ICONE-10 Conference, Arlington USA (April 14-18, 2002)
|
37 |
B.R. Sehgal, 'Stabilization and termination of severe accidents in LWRs', Nucl. Eng. Design 236, 1941 (2006)
DOI
ScienceOn
|
38 |
H. Alsmeyer, B. Spencer, W. Fromm, 'The COMET concept for cooling of ex-vessel corium melts', Proceedings of ICONE-6 Conference, San Diego, USA (1998)
|
39 |
M.J. Konovalikhin and B.R. Sehgal, 'Investigation of volumetrically heated debris bed quenching', Proceedings of ICONE-9 Meeting, Nice, France (April 2001)
|
40 |
T.G. Theofanous et al. 'The probability of liner failure in a Mark-1 containment' NUREG/CR-5423 and NUREG/CR-5960 U.S. Nuclear Regulatory Commission Reports (1993)
|
41 |
S. Dorofeev et. al., 'Flame acceleration limits for nuclear safety applications', Proc. CSARP Meeting, Albuqurque, New Mexico (1999)
|
42 |
T.G. Theofanous et al., 'In-vessel coolability and retention of a core melt' DOE/ID-10460, U.S. Department of Energy Report (1995)
|
43 |
I. Huhtiniemi and D. Magallon, 'Insight into steam explosions with corium melts in KROTOS', Proceedings Nuclear Reactor Thermal Hydraulics-9 Meeting (1999)
|
44 |
G. Berthoud and C. Brayer, 'First vapour explosion calculations performed with MC3D code', Proc. CSNI specialists meeting on FCIs, Tokai, Japan (1997)
|