Published January 1991 | Version v1
Report Restricted

Calculation of test leakage rate for a spent fuel cask

Description

Prior to shipment a spent fuel cask must be leak-tested to ensure that no radioactive releases greater than regulatory limits will occur during normal transport and accident conditions. In this paper we present a method for estimating the releasable radioactive material from a cask and the associated leak-testing requirements to ensure compliance with 10 CFR 71 regulations. We used the ANSI N14.5 standard to calculate the test-leakage rates from the maximum permissible releases determined from regulations

Availability note (English)

MF available from INIS under the Report Number; OSTI as DE92009464; NTIS; INIS; US Govt. Printing Office Dep.

Files

Restricted

The record is publicly accessible, but files are restricted to users with access.

Additional details

Publishing Information

Imprint Pagination
5 p.
Report number
UCRL-JC--106203

Conference

Title
Annual meeting of the American Nuclear Society (ANS).
Dates
2-6 Jun 1991.
Place
Orlando, FL (United States).

Optional Information

Contract/Grant/Project number
Contract W-7405-ENG-48
Funding organization
USDOE, Washington, DC (United States).
Secondary number(s)
CONF-910603--26.