THERMAL EVALUATION OF DIFFERENT DRIFT DIAMETER SIZES
The purpose of this calculation is to estimate the thermal response of a repository-emplaced waste package and its corresponding drift wall surface temperature with different drift diameters. The case examined is that of a 21 pressurized water reactor (PWR) uncanistered fuel (UCF) waste package loaded with design basis spent nuclear fuel assemblies. This calculation evaluates a 3.5 meter to 6.5 meter drift diameter range in increments of 1.0 meters. The time-dependent temperatures of interest, as determined by this calculation, are the spent nuclear fuel cladding temperature, the waste package surface temperature, and the drift wall surface temperature.
- Research Organization:
- Office of Scientific and Technical Information (OSTI), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- NA
- OSTI ID:
- 862267
- Report Number(s):
- BBA000000-01717-0210-00023 REV 00; MOL.19981110.0001 DC#20258; TRN: US0600707
- Country of Publication:
- United States
- Language:
- English
Similar Records
Uncanistered Spent Nuclear fuel Disposal Container System Description Document
EMPLACEMENT SCALE THERMAL EVALUATIONS OF LARGE AND SMALL WP DESIGNS (SCPB: N/A)
RADIOLOGICAL RELEASES DUE TO AIR AND SILICA DUST ACTIVATION IN EMPLACEMENT DRIFTS
Technical Report
·
Thu Oct 12 00:00:00 EDT 2000
·
OSTI ID:862267
EMPLACEMENT SCALE THERMAL EVALUATIONS OF LARGE AND SMALL WP DESIGNS (SCPB: N/A)
Technical Report
·
Mon Dec 18 00:00:00 EST 1995
·
OSTI ID:862267
RADIOLOGICAL RELEASES DUE TO AIR AND SILICA DUST ACTIVATION IN EMPLACEMENT DRIFTS
Technical Report
·
Wed May 07 00:00:00 EDT 2003
·
OSTI ID:862267