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The contribution of spent fuel shipping cask residual contamination to the transporation source term
Mings, W.J.; Pauspathi, V.; Sandoval, R.P.; Jordan, H.; Einziger, R.E.
Sandia National Labs., Albuquerque, NM (USA)1988
Sandia National Labs., Albuquerque, NM (USA)1988
AbstractAbstract
[en] The US Code of Federal Regulations for the packaging and transportation of radioactive material, 10 CFR Part 71, requires that all shipping packages used to transport irradiated reactor fuel in the US be designed, constructed, and prepared for shipment so that: ''(1) under the tests specified in Section 71.71 (Normal Conditions of Transport), there be no loss or dispersal of radioactive contents as demonstrated to a sensitivity of 10/sup /minus/6/ A2 per hour; and (2) under the tests specified in Section 71.73 (Hypothetical Accident Conditions), there be no escape of krypton-85 exceeding 10, 000 Ci in one week and no escape of other radioactive material exceeding a total amount of A2 in one week.'' The quantity A2 is derived from dosimetric models and varies for each nuclide in accordance with its radiotoxicity. 6 refs., 1 tab
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1988; 6 p; Joint meeting of the European Nuclear Society and the American Nuclear Society; Washington, DC (USA); 30 Oct - 4 Nov 1988; CONF-881011--18; Available from NTIS, PC A02/MF A01; 1 as DE88014970; Portions of this document are illegible in microfiche products.
Record Type
Report
Literature Type
Conference; Numerical Data
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