1997
DOI: 10.2172/582272
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Transportation and packaging issues involving the disposition of surplus plutonium as MOX fuel in commercial LWRs

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“…Clearly, all the dose rates are well within the limits required by 10 CFR 71.47 and 10 CFR 71.51(a) (2). 6 The secondary gamma dose rates include contributions from prompt fission gamma rays (because of induced fission), as well as that from neutron capture.…”
Section: Shielding Analysismentioning
confidence: 69%
“…Clearly, all the dose rates are well within the limits required by 10 CFR 71.47 and 10 CFR 71.51(a) (2). 6 The secondary gamma dose rates include contributions from prompt fission gamma rays (because of induced fission), as well as that from neutron capture.…”
Section: Shielding Analysismentioning
confidence: 69%
“…Details of the fuel-handling-operations interface requirements for power plants are discussed in Appendix C. Appendix C data were derived in part from information developed for DOE and reported in site and facility waste transportation planning documents (SPDs) [see "Site and Facility Waste Transportation Planning Documents Status and Findings" 12 …”
Section: Power Plant Interfacementioning
confidence: 99%
“…Supporting this effort, ORNL prepared a report describing the transportation and packaging issues involved in transporting MOX fresh fuel in new Type B(U)F packages by safe secure trailer (SST) between the MOX fuel fabrication facility and the commercial reactors. 2 SSTs would be required to provide physical protection for the weapons-grade MOX fuel in transit. PAS was followed by release of a draft Request for Proposals (RFP) 3 in November 1997.…”
Section: Introductionmentioning
confidence: 99%