This report provides information on the inventory of spent nuclear fuel (SNF) in the United States located at Nuclear Power Reactor and Independent Spent Fuel Storage Installation sites, as well as SNF and reprocessing waste located at U.S. Department of Energy sites and other research and development centers as of the end of calendar year 2021.
The purpose of this calculation is to document the Three Mile Island Unit 1 pressurized water reactor {PWR) reactivity calculations performed as part o f the commercial reactor critical (CRC) evaluation program. CRC evaluation reactivity calculations are performed at a number of statepoints, representing reactor start-up critical conditions at either beginning of life (BOL), beginning of cycle (BOC), or mid- cycle when the reactor resumed operation after a shutdown.
The purpose of this calculation is to document the Three Mile Island Unit 1 pressurized water reactor (PWR) fuel depletion calculations performed as part of the commercial reactor critical (CRC) evaluation program. The CRC evaluations support the development and validation of the neutronics models used for criticality analyses involving commercial spent nuclear fuel in a geologic repository.
Transport of the damaged core materials from the Unit 2 reactor of the Three
Mile Island Nuclear Power Station (TMI-2) to the Idaho National Engineering Laboratory
(INEL) for examination and storage presented many technical and institutional
challenges, including assessing the ability to transport the damaged core;
removing and packaging core debris in ways suitable for transport; developing a
transport package that could both meet Federal regulations and interface with the
The General Accounting Office examined DOE's "program to ship damaged nuclear fuel from the Three Mile Island nuclear power plant, near Harrisburg, Pennsylvania, to the Idaho National Engineering Laboratory." The report was requested by Reps. William L. Clay, Richard A. Gephardt, and Alan Wheat.
The objective of this calculation is to evaluate the criticality potential for co-disposal waste packages affected by an igneous intrusion disruptive event in the emplacement drifts. The scope of this calculation is limited to U.S. Department of Energy (DOE) Spent Nuclear Fuel (SNF) types in DOE standardized SNF canisters or Multi-Canister Overpack (MCO) Canisters.
Following the massive earthquake and resulting tsunami damage in March of 2011 at the Fukushima
Daiichi nuclear power plant in Japan, interest was amplified for what was done for recovery at the Three
Mile Island Unit 2 (TMI-2) in the United States following its meltdown in 1979. Many parallels could be
drawn between to two accidents. This paper presents the results of research done into the TMI-2 recovery
effort and its applicability to the Fukushima Daiichi cleanup. This research focused on three topics:
