The Container Analysis Fire Environment (CAFE) computer code is used to simulate the response of a generic legal-weight-truck package to 3h fires. Simulations are performed with the package centered 1m above a 7.2m-diameter JP-8 fuel pool. They are also performed with the package horizontally offset from that location by 1m and 2.5m. Simulations without impact limiters are performed to quantify the level of thermal protection they provide. The minimum fire duration that causes the seal to reach its temperature of concern is determined for each configuration. When the center of the no-impact limiter package is within 2.5m of the pool center, 0.7h fires are capable of causing the seal to reach its temperature of concern. By contrast, the intact package protects the seal in fires that last more than 2h. These results help risk analysts understand the effect of package position and the role of impact limiters on accident consequences.

1.
U. S. Nuclear Regulatory Commission
, 2000, “
Packaging and Transportation of Radioactive Material
,” Rules and Regulations, Title 10, Part 71, Code of Federal Regulations.
2.
Fischer
,
L. E.
,
Chou
,
C. K.
,
Gerhard
,
M. A.
,
Kimura
,
C. Y.
,
Martin
,
R. W.
,
Mensing
,
R. W.
,
Mount
,
M. E.
, and
Whitte
,
M. C.
, 1987, “
Shipping Container Response to Severe Highway and Railway Accident Conditions
,”
Lawrence Livermore National Laboratory
Report No. NUREG∕CR-4829, Livermore, CA.
3.
Sprung
,
J. L.
,
Ammerman
,
D. J.
,
Breivik
,
N. L.
,
Dukart
,
R. J.
,
Kanipe
,
F. L.
,
Koski
,
J. A.
,
Mills
,
G. S.
,
Neuhauser
,
K. S.
,
Radloff
,
H. D.
,
Weiner
,
R. F.
, and
Yoshimura
,
H. R.
, 2000, “
Reexamination of Spent Fuel Shipment Risk Estimates
,”
U. S. Nuclear Regulatory Commission
Report No. NUREG∕CR-6672, Washington, DC.
4.
Greiner
,
M.
,
Shin
,
S.
,
Faulkner
,
R. J.
, and
Wirtz
,
R. A.
, 1998, “
Transport Cask Response to Regulatory Format Thermal Events, Part 1: Rail Package
,”
Int. J. Radioact. Mater. Transp.
0957-476X,
9
(
3
), pp.
187
192
.
5.
Greiner
,
M.
,
Faulkner
,
R. J.
, and
Jin
,
Y. Y.
, 1998, “
Transport Cask Response to Regulatory Format Thermal Events, Part 2: Truck Cask
,”
Int. J. Radioact. Mater. Transp.
0957-476X,
9
(
3
), pp.
193
198
.
6.
Greiner
,
M.
,
Are
,
N.
,
Lopez
,
C.
, and
Suo-Anttila
,
A.
, 2004, “
Effect of Small Long-Duration Fires on a Spent Nuclear Fuel Transport Package
,”
Institute of Nuclear Materials Management 45th Annual Meeting
,
Orlando, FL
, July 18–22.
7.
Lopez
,
C.
,
Koski
,
J. A.
, and
Suo-Anttila
,
A.
, 2003, “
Development and Use of the CAFE-3D Code for Analysis of Radioactive Material Packages in Fire Environment
,” presented at the
INMM 44th Annual Meeting
,
Phoenix, AZ
, Jul.
8.
Greiner
,
M.
, and
Suo-Anttila
,
A. J.
, 2006, “
Radiation Heat Transfer and Reaction Chemistry Models for Risk Assessment Compatible Fire Simulations
,”
J. Fire Protect. Eng.
1042-3915,
16
, pp.
79
103
.
9.
Greiner
,
M.
, and
Suo-Anttila
,
A. J.
, 2004, “
Validation of the Isis-3D Computer Code for Simulating Large Pool Fires Under a Variety of Wind Conditions
,”
ASME J. Pressure Vessel Technol.
0094-9930,
126
, pp.
360
368
.
10.
Gritzo
,
L. A.
,
Sivathaunu
,
Y. R.
, and
Gill
,
W.
, 1998, “
Transient Measurements of Radiative Properties, Soot Volume Fraction, and Soot Temperature in a Large Pool Fire
,”
Combust. Sci. Technol.
0010-2202,
139
, pp.
113
136
.
11.
Murphy
,
J. J.
, and
Shaddix
,
C. R.
, 2004, “
Soot Properties and Species Measurements in a Two-Meter Diameter JP-8 Pool Fire: 2003 Test Series
,” Sandia Report No. Sand2004-8085.
12.
Modest
,
M. F.
, 2003,
Radiative Heat Transfer
,
2nd ed.
,
Academic
,
New York
.
13.
Fire Protection Handbook
, 1997,
18th ed.
,
National Fire Protection Association
,
Boston
.
14.
Are
,
N.
,
Greiner
,
M.
, and
Suo-Anttila
,
A.
, 2005, “
Benchmark of a Fast Running Computational Tool for Analysis of Massive Radioactive Material Packages in Fire Environments
,”
ASME J. Pressure Vessel Technol.
0094-9930,
127
, pp.
508
514
.
15.
Greiner
,
M.
, and
Chalasani
,
N. R.
, 2004, “
Fire Durations of Concern for Legal Weight Truck Packages With Different Placements Relative to a 7.2‐m-diameter Pool Fire
,” Nevada Agency of Nuclear Projects Final Report.
16.
Kramer
,
A.
,
Greiner
,
M.
,
Koski
,
J. A.
,
Suo-Anttila
,
A.
, and
Lopez
,
C.
, 2003, “
Measurements of Heat Transfer to a Massive Cylindrical Object Engulfed in a Regulatory Pool Fire
,”
ASME J. Heat Transfer
0022-1481,
125
, pp.
110
117
.
17.
Gritzo
,
L. A.
,
Moya
,
J. A.
, and
Murray
,
D.
, 1997, “
Fire Characterization and Object Thermal Response for a Large Flat Plate Adjacent to a Large JP4 Fuel Fire
,” Sandia National Laboratories Report No. SAND97-0047, p.
22
.
18.
NAC International
, 2000, “
Safety Analysis Report for the NAC Legal Weight Truck Cask
,” Nuclear Regulatory Commission Accession No. ML003677743.
19.
Incropera
,
F. P.
, and
DeWitt
,
D. P.
, 1996,
Fundamentals of Heat and Mass Transfer
,
4th ed.
,
Wiley
,
New York
.
20.
Westinghouse Electric Company
, 2000, HalfPACT Safety Analysis Report, Rev. 1.
21.
Manteufel
,
R. D.
, and
Todreas
,
N. E.
, 1994, “
Effective Thermal Conductivity and Edge Conductance Model for a Spent-Fuel Assembly
,”
Nucl. Technol.
0029-5450,
105
, pp.
421
440
.
22.
Bahney
,
R. H.
, and
Lotz
,
T. L.
, 1996, “
Spent Nuclear Fuel Effective Thermal Conductivity Report
,” TRW Environmental Safety Systems, Inc. Document Identifier No. BBA000000-01717-5705-00010 Rev 00,
154
pages.
23.
Araya Gómez
,
P.
, and
Greiner
,
M.
, 2005, “
Simulations of Heat Transfer Within the Fuel Assembly∕Backfill Gas Region of Transport Packages
,”
2005 ASME Pressure Vessel and Piping Conference
,
Denver, CO
, July
17
21
, Paper No. PVP2005-7170.
24.
Office of Civilian Radioactive Waste Management
, 1993, US Department of Energy Multi-Purpose Canister (MPC) Implementation Program Conceptual Design Phase Report, DOC IC: A20000000-00811-5705-00005.
You do not currently have access to this content.