The purpose of this calculation is to perform waste-form specific nuclear criticality safety calculations to aid in establishing criticality safety design criteria, and to identify design and process parameters that are potentially important to the criticality safety of Department of Energy (DOE) standardized Spent Nuclear Fuel (SNF) canisters.
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
More than 45 million shipments of radioactive materials have taken place in the United States
over the last three decades, with a current rate of about three million per year. The majority of
these radioactive shipments consist of radiopharmaceuticals, luminous dials and indicators,
smoke detectors, contaminated clothing and equipment, and research and industrial sources.
Fewer than 3,500, or 0.01%, have been involved in any sort of accident, incident, or anything
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
he U.S. Nuclear Regulatory Commission (NRC) regulates storage of spent nuclear fuel (SNF) from commercial nuclear power plants. An increasing amount of the SNF in storage is in dry storage systems, mostly at current and decommissioned plants. As directed by the Commission (in SRM-COMSECY-10-0007; December 6, 2010), in expectation of continued use of dry storage for extended periods of time, the NRC staff is examining the technical needs and potential changes to the regulatory framework that may be needed to continue licensing of SNF storage over periods beyond 120 years.
The purpose of the Foreign Research Reactor (FRR) Spent Nuclear Fuel (SNF) Shipments Institutional Program was to meet the goals and commitments of the Implementation Strategy Plan for the FRR SNF Shipments. This program provided a systematic approach to planning, implementing, evaluating, and validating preparedness for the first west coast shipment of SNF from Asian countries to the Idaho National Engineering and Environmental Laboratory (INEEL).
An Act to provide for the development of repositories for the disposal of high-level radioactive waste and spent nuclear fuel, to establish a program of research, de- velopment, and demonstration regarding the disposal of high-level radioactive waste and spent nuclear fuel, and for other purposes.
This report evaluates the radiological impacts during postulated accidents associated with the
transportation of spent nuclear fuel to the proposed Yucca Mountain repository, using the
RADTRAN 5.5 computer code developed by Sandia National Laboratories. RADTRAN 5.5 can
be applied to estimate the risks associated both with incident-free transportation of radioactive
materials as well as with accidents that may be assumed to occur during transportation. Incidentfree
transportation risks for transport of spent nuclear fuel to Yucca Mountain were evaluated in
The U.S. Nuclear Waste Technical Review Board (Board) is tasked by the amendments to the Nuclear Waste Policy Act of 1982 to independently evaluate U. S. Department of Energy (DOE) technical activities for managing and disposing of used nuclear fuel and high-level radioactive waste. This report was prepared to inform DOE and Congress about the current state of the technical basis for extended dry storage1 of used fuel and its transportation following storage.
This Plan outlines the Department of Energy’s (DOE) current strategy and planning for
developing and implementing the transportation system required to transport spent nuclear fuel
(SNF) and high-level radioactive waste (HLW) from where the material is generated or stored to
the proposed repository at Yucca Mountain, Nevada. The Plan describes how DOE’s Office of
Civilian Radioactive Waste Management (OCRWM) intends to develop and implement a safe,
secure and efficient transportation system and how stakeholder collaboration will contribute to
