Skip to main content
OSTI.GOVU.S. Department of Energy Office of Scientific and Technical Information
U.S. Department of Energy
Office of Scientific and Technical Information
 

Thermal-hydraulic analyses of the TN-24P cask loaded with consolidated and unconsolidated spent nuclear fuel

Conference ·
OSTI ID:5273184
; ; ;

This paper presents the results of comparisons of COBRA-SFS (spent fuel storage) temperature predictions with experimental data from the TN-24P (Transnuclear) spent fuel storage cask loaded with unconsolidated and consolidated spent PWR fuel. Peak cladding temperature predictions using the COBRA-SFS code are compared with test data and predicted axial and radial temperature distributions are compared with measured temperature profiles. The pre-test accuracy of the COBRA-SFS code in predicting temperature distributions is discussed, along with the effect of post-test model improvements on temperature predictions. This paper also briefly describes the COBRA-SFS code, which is designed to accurately predict flow and temperature distributions in spent nuclear fuel storage and transportation systems. 6 refs., 14 figs.

Research Organization:
Pacific Northwest Lab., Richland, WA (USA)
Sponsoring Organization:
DOE/RW
DOE Contract Number:
AC06-76RL01830
OSTI ID:
5273184
Report Number(s):
PNL-SA-16240; CONF-890601--3; ON: DE90005542
Country of Publication:
United States
Language:
English

Similar Records

Testing and analyses of the TN-24P PWR spent-fuel dry storage cask loaded with consolidated fuel
Technical Report · Tue Jan 31 23:00:00 EST 1989 · OSTI ID:6372210
The TN-24P PWR spent-fuel storage cask: Testing and analyses: Interim report
Technical Report · Tue Mar 31 23:00:00 EST 1987 · OSTI ID:6498617
HYDRA and COBRA-SFS temperature calculations for CASTOR-IC, REA-2023, CASTOR-V/21, and TN-24P
Conference · Fri Feb 28 23:00:00 EST 1986 · OSTI ID:5620790

Related Subjects

052002* -- Nuclear Fuels-- Waste Disposal & Storage
053000 -- Nuclear Fuels-- Environmental Aspects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
C CODES
CASKS
COMPARATIVE EVALUATIONS
COMPUTER CODES
CONTAINERS
DATA
ENERGY SOURCES
EXPERIMENTAL DATA
FLUID MECHANICS
FUELS
HIGH-LEVEL RADIOACTIVE WASTES
HYDRAULICS
INFORMATION
MANAGEMENT
MATERIALS
MECHANICS
NUCLEAR FUELS
NUMERICAL DATA
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE DISPOSAL
RADIOACTIVE WASTES
REACTOR MATERIALS
SPENT FUEL CASKS
SPENT FUEL STORAGE
SPENT FUELS
STORAGE
TEMPERATURE EFFECTS
THEORETICAL DATA
THERMAL ANALYSIS
TRANSPORT
UNDERGROUND DISPOSAL
WASTE DISPOSAL
WASTE MANAGEMENT
WASTES