Testing and COBRA-SFS analysis of the VSC-17 ventilated concrete, spent fuel storage cask Page: 2 of 12
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TESTING AND COBRA-SFS ANALYSIS
OF THE VSC-17 VENTILATED CONCRETE, SPENT FUEL STORAGE CASK
Mlkal A. McKinnon
Ryan E. Dodgo
Pacific Northwest Laboratory
P.O. Box 999
Richland, WA 99352
A performance test of a Pacific Sierra Nuclear VSC-17
ventilated concrete storage cask loaded with 17 canis-
ters of consolidated PWR spent fuel generating approxi-
mately 15 kW was conducted. a The performance test
Included measuring the cask surface, concrete, air
channel surface, and fuel tomperaturos, as well as cask
surface gamma and neutron dose rates. Testing was
performed using vacuum, nitrogen, and helium backfill
environments. Pretest predictions of cask thermal per-
formance wore made using the COBRA-SFS computer
code. Analysis results wore within 15"C of measured
peak fuel temperature, Peak fuel temperature for nor-
mal operation was 321°C. In general, the surface dose
rates were less than 30 mrem/h on the side of the cask
and 40 mrem/h on the top of the cask.
Since the enactment of the Nuclear Waste Policy
Act in 1982, large metal spent fuel storage casks have
boon evaluated through tests and analyses for Interim
or lag storage at utility reactors and for use in Federal
facilities associated with storage/disposal systems.
Conceptual designs and analyses for interim or lag
storage Indicate that concrete spent fuel storage casks
may bo economically and technically competitive with
metal casks. Therefore, it was desirable to conduct a
“ The work was performed by the Pacific Northwest
Laboratory (PNL.) and the Idaho National Engineering
Laboratory (INEL) for a cooperative agreement between
the U.S. Department of Energy, Office of Civilian'
Radioactive Waste Management and Pacific Sierra
Nuclear with support from the Wisconsin Electric and
Power Company and the Electric Power Research
Institute. PNL is operated for DOE by Batlelle Memorial
Institute under contract DE-AC06-76RLO 1830.
Richard C. Schmitt
Idaho National Engineering Laboratory
P.O. Box 1625, TAN 602, MS-9109
Idaho Falls, ID 03405
Concrete Cask Testing (CCT) Project to evaluate the
benefits of concrete as a storage cask material and to
provide assistance In licensing activities if appropriate.
In 1907, DOE Office of Civilian Radioactlvo Waste
Management Initiated activities to obtain concrete stor-
age modules for testing that could be used at reactors
or Federal interim storago or disposal sites. The mod-
ules/casks were to be different from those previously
tested at GE-Morrls by DOE and EPRI, at INEL by DOE,
Virginia Power, and EPRI at H.B. Robinson Nuclear
Reactor by DOE, Carolina Power and Light, and EPRI10
but were to bo similar to those concepts that could be
employed at nuclear reactor sites and Federal facilities.
In late 1988 DOE entered into a Cooperative Agreement
with Pacific Sierra Nuclear Associates (PSN) to demon-
strate the performance of a small ventilated concrote
This summary report focuses on a heat transfer
and shielding performance test conducted on a Pacific
Sierra Nuclear VSC-17 pressurlzod-wator reactor (PWR)
spent fuel storago cask loaded with consolidated spent
fuel. Additional information of the performance test can
be found in reference 7. The performance testing con-
sisted of pretest preparations, performance testing, and
post-test activities. Pretest preparations Involved
performing predictive code analyses and conducting
cask-handling dry (cold) runs. The performance tests
Included six runs with the cask In a vertical orientation,
four vent blockage conditions, and three backfill
The PSN VSC-17 spent fuel storage cask system
Is a passive device for storing 17 assemblies/canlsters
of spent nuclear fuel, The VSC-17 system consists of
an outer Ventilated Concrete Cask (VCC) and an inner
Multi-Assembly Sealed Basket (MSB). The cask system
is shown in Figure 1. Most of the decay heat, gener-
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McKinnon, M.A.; Dodge, R.E. (Pacific Northwest Lab., Richland, WA (United States)) & Schmitt, R.C. (EG and G Idaho, Inc., Idaho Falls, ID (United States)). Testing and COBRA-SFS analysis of the VSC-17 ventilated concrete, spent fuel storage cask, article, April 1, 1992; Richland, Washington. (digital.library.unt.edu/ark:/67531/metadc1094086/m1/2/: accessed February 17, 2019), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.