Concrete Shield Performance of the VSC-17 Spent Nuclear Fuel Cask
Conference
·
OSTI ID:911714
The VSC-17 Spent Nuclear Fuel Storage Cask was surveyed for degradation of the concrete shield by radiation measurement, temperature measurement, and ultrasonic testing. No general loss of shielding function was identified.
- Research Organization:
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- DE-AC07-99ID-13727
- OSTI ID:
- 911714
- Report Number(s):
- INL/CON-06-11215; TRN: US0800100
- Resource Relation:
- Conference: 2006 International High Level Radioactive Waste Management Conference,Las Vegas, NV,04/30/2006,05/04/2006
- Country of Publication:
- United States
- Language:
- English
Similar Records
Concrete Shield Performance of the VSC-17 Spent Nuclear Fuel Cask
Inspection and Gamma-Ray Dose Rate Measurements of the Annulus of the VSC-17 Concrete Spent Nuclear Fuel Storage Cask
Nondestructive Evaluation of the VSC-17 Cask
Conference
·
Sat Apr 01 00:00:00 EST 2006
·
OSTI ID:911714
+3 more
Inspection and Gamma-Ray Dose Rate Measurements of the Annulus of the VSC-17 Concrete Spent Nuclear Fuel Storage Cask
Technical Report
·
Sat Sep 01 00:00:00 EDT 2007
·
OSTI ID:911714
Nondestructive Evaluation of the VSC-17 Cask
Technical Report
·
Sun Jan 01 00:00:00 EST 2006
·
OSTI ID:911714
+5 more