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Victor G. Snell
Observed names:
Snell, Victor G.,
V. G. Snell,
V.G. Snell,
VG Snell
Institution:
Atomic Energy (Canada)
Observed institutions:
Atomic Energy (Canada),
McMaster University
OpenAlex ID:
A5045388553
Accident Analysis for Nuclear Power Plants
2002
·
C.M. Allison
, E. Balabanov
, et al.
·
54
Accident Analysis for Nuclear Power Plants with Pressurized Water Reactors
2003
·
C.M. Allison
, E. Balabanov
, et al.
·
28
Coolability of Severely Degraded Candu Cores
1995
·
J. T. Rogers
, D. A. Meneley
, et al.
·
Proceedings of the International Symposium
·
13
Severe Core Damage Experiments and Analysis for CANDU Applications (C069)
2003
·
P. Mani Mathew
, Alex White
, et al.
·
NCSU Libraries Repository (North Carolina State University Libraries)
·
10
CANDU-Specific Severe Core Damage Accident Experiments in Support of Level 2 PSA
2001
·
P. Mani Mathew
, Bill Kupferschmidt
, et al.
·
NCSU Libraries Repository (North Carolina State University Libraries)
·
8
PDF
Source term and radiological consequences of the Chernobyl accident.
1987
·
R. Mourad
, V.G. Snell
·
Transactions of the American Nuclear Society
·
6
IAEA Safety Report on Accident Analysis for Nuclear Power Plants
2000
·
M.W. Jankowski
, J. Misak
, et al.
·
4
Safety and Licensing Aspects of Power Reactor Reactivity Coefficients
2012
·
Nik K. Popov
, Victor G. Snell
·
Volume 4: Codes, Standards, Licensing, and Regulatory Issues; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Instrumentation and Co
·
3
Chernobyl : a Canadian technical perspective
1987
·
J Q Howieson
, V.G. Snell
·
CERN Document Server (European Organization for Nuclear Research)
·
3
Licensing the ACR in the USA - A Status Report
2004
·
V.G. Snell
, Vince Langman
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
2
A quick look at the post accident review meeting (PARM)
1986
·
A.R. Dastur
, R P Osborne
, et al.
·
1
Application of Up-Front Licensing
2024
·
Grant, Scott D.
, Snell, Victor G.
·
Canadian Nuclear Society Proceedings
CANDU 9: The CANDU Product to Meet Customer and Regulator Requirements Now and in the Future
2024
·
Snell, Victor G.
, Webb, John R.
·
Canadian Nuclear Society Proceedings
Pre-Project Regulatory Reviews of ACR-1000"T"M and EC6"T"M
2011
·
N.K. Popov
, R.A. Ion
, et al.
Icone15-10806 the Management of Severe Accidents in Modern Pressure Tube Reactors
2007
·
N.K Popov
, P. Santamaura
, et al.
·
The Proceedings of the International Conference on Nuclear Engineering (ICONE)
PDF
Icone15-10680 Acr-1000 Severe Accident Program
2007
·
N.K. Popov
, S.A. Bajwa
, et al.
·
The Proceedings of the International Conference on Nuclear Engineering (ICONE)
PDF
ACR-1000: Enhanced Response to Severe Accidents
2006
·
NK Popov
, P. Santamaura
, et al.
ACR-1000: Licensing Status
2006
·
NK Popov
, VG Snell
, et al.
Single channel flow blockage accident phenomena identification and ranking table (PIRT) for the advanced Candu reactor
2004
·
N.K. Popov
, A. Abdul‐Razzak
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
Large-Break Loss-of-Coolant Accident Phenomena Identification and Ranking Table (PIRT) for the Advanced CANDU Reactor
2004
·
N. Popov
, H. E. Sills
, et al.
·
The Proceedings of the International Conference on Nuclear Engineering (ICONE)
Computer Code Applicability Assessment for the Advanced CANDU Reactor
2004
·
D. J. Wren
, N. Popov
, et al.
·
The Proceedings of the International Conference on Nuclear Engineering (ICONE)
Validation of Physics and Thermalhydraulics Computer Codes for Advanced CANDU Reactor Applications
2004
·
D. J. Wren
, N. Popov
, et al.
·
The Proceedings of the International Conference on Nuclear Engineering (ICONE)
CANDU Severe Accident Resistance
1999
·
M. Bonechi
, V.G. Snell
·
NCSU Libraries Repository (North Carolina State University Libraries)
CANDU safety-status and direction
1993
·
V.G. Snell
, P.J. Allen
·
Transactions of the American Nuclear Society
The SLOWPOKE licensing model
1992
·
V.G. Snell
, F. Takáts
, et al.
·
Nuclear Engineering and Design
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Works count:
29
Citation count:
132
H-index:
6
I10-index:
4
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