skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: STRONTIUM-90 SHIPPING CASK DESIGN CRITERIA AND HAZARDS EVALUATION

Abstract

A cask was designed for shipping a maximum of 168,000 curies of Sr/sup 90/ along with the associated impurities from Hanford to the Martin Nuclear Company and Oak Ridge National Laboratories. The cask was designed to completely contain the Sr/sup 90/ while being decelerated at greater than 50 G. The cask is protected by an external buIfer to assure that the deceleration does not exceed 50 G and also distribute the forces arising from striking sharp objects or solid surfaces. The cask has sufficient shielding to reduce the radiation levels to those required by the ICC. The cask surface temperature will be about 230 deg F and the maximum fission product temperature will be about 453 deg F during normal operation with the maximum permissible heat generation rate of 1l,600 Btu/ hour. Before releasing the cask the heat generation rate and the pressure buildup must be measured. To assure safe shipment lt is necessary that the decay heat rate does not exceed 11,600 Btu -hour, that the equilibrium pressure is less than 100 psig, and that there are no helium leaks at the cask closures. Procedures for loading and unloading were developed. (auth)

Authors:
Publication Date:
Research Org.:
General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
OSTI Identifier:
4831966
Report Number(s):
HW-68081
NSA Number:
NSA-16-003260
DOE Contract Number:  
W-31-109-ENG-52
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-62
Country of Publication:
United States
Language:
English
Subject:
HEALTH AND SAFETY; FISSION PRODUCTS; HEATING; HELIUM; IMPURITIES; PLANNING; QUANTITATIVE ANALYSIS; RADIATION DOSES; RADIOACTIVITY; SAFETY; SHELLS; SHIELDING; STABILITY; STRONTIUM 90; SURFACES; TEMPERATURE; VOLUME

Citation Formats

Smith, C W. STRONTIUM-90 SHIPPING CASK DESIGN CRITERIA AND HAZARDS EVALUATION. United States: N. p., 1961. Web.
Smith, C W. STRONTIUM-90 SHIPPING CASK DESIGN CRITERIA AND HAZARDS EVALUATION. United States.
Smith, C W. Fri . "STRONTIUM-90 SHIPPING CASK DESIGN CRITERIA AND HAZARDS EVALUATION". United States.
@article{osti_4831966,
title = {STRONTIUM-90 SHIPPING CASK DESIGN CRITERIA AND HAZARDS EVALUATION},
author = {Smith, C W},
abstractNote = {A cask was designed for shipping a maximum of 168,000 curies of Sr/sup 90/ along with the associated impurities from Hanford to the Martin Nuclear Company and Oak Ridge National Laboratories. The cask was designed to completely contain the Sr/sup 90/ while being decelerated at greater than 50 G. The cask is protected by an external buIfer to assure that the deceleration does not exceed 50 G and also distribute the forces arising from striking sharp objects or solid surfaces. The cask has sufficient shielding to reduce the radiation levels to those required by the ICC. The cask surface temperature will be about 230 deg F and the maximum fission product temperature will be about 453 deg F during normal operation with the maximum permissible heat generation rate of 1l,600 Btu/ hour. Before releasing the cask the heat generation rate and the pressure buildup must be measured. To assure safe shipment lt is necessary that the decay heat rate does not exceed 11,600 Btu -hour, that the equilibrium pressure is less than 100 psig, and that there are no helium leaks at the cask closures. Procedures for loading and unloading were developed. (auth)},
doi = {},
url = {https://www.osti.gov/biblio/4831966}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1961},
month = {1}
}

Technical Report:
Other availability
Please see Document Availability for additional information on obtaining the full-text document. Library patrons may search WorldCat to identify libraries that may hold this item. Keep in mind that many technical reports are not cataloged in WorldCat.

Save / Share: