In 2007 the OECD Nuclear Energy Agency (NEA) Radioactive Waste Management Committee
(RWMC) launched a four-year project on the topics of reversibility and retrievability in geological
disposal. The goal of the project studies and activities (www.oecd-nea.org/rwm/rr) was to
acknowledge the range of approaches to reversibility and retrievability (R&R), rather than to
recommend a specific approach, and to provide a basis for reflection rather than to lead towards

This paper provides a brief description of the United States Nuclear Regulatory Commission (NRC) and its regulatory process for the current nuclear fuel cycle for light water power reactors (LWRs). It focuses on the regulatory framework for the licensing of facilities in the fuel cycle. The first part of the paper provides an overview of the NRC and its regulatory program including a description of its organization, function, authority, and responsibilities.

Burnup credit (BUC) is a concept applied in the criticality safety analysis of spent nuclear fuel
in which credit or partial credit is taken for the reduced reactivity worth of the fuel due to both fissile
depletion and the buildup of actinides and fission products that act as net neutron absorbers.
Typically, a two-step process is applied in BUC analysis: first, depletion calculations are performed
to estimate the isotopic content of spent fuel based on its burnup history; second, three-dimensional

This study provides a technical basis for informing policy decisions regarding strategies for the management and permanent disposal of spent nuclear fuel (SNF) and high-level radioactive waste (HLW) in the United States requiring geologic isolation. Relevant policy questions this study can help inform include the following: Is a “one-size-fits–all” repository a good strategic option for disposal? Do

The main objective of this report is to identify conditions which affect public concern (either
increase or decrease) and political acceptance for developing and implementing programmes
for geologic disposal of long-lived radioactive waste. It also looks how citizens and relevant
actors can be associated in the decision making process in such a way that their input is
enriching the outcome towards a more socially robust and sustainable solution. Finally, it
aims at learning from the interaction how to optimise risk management addressing needs and

A set of 16 geologic disposal concepts is described in sufficient detail for rough-order-of-magnitude repository cost estimates, for disposal of spent nuclear reactor fuel in generic crystalline, argillaceous, and salt host geologic media. The description includes total length, diameter, and volume for all underground shafts, ramps, drifts and large-diameter borings. Basic types of ground support are specified. Total repository capacity is assumed to be approximately 140,000 MT of spent fuel, but concepts are described in terms of modular panels each containing 10,000 MT.