Sustainable Development Report: Managing Today to Prepare for Tomorrow
Sustainable Development Report: Managing Today to Prepare for Tomorrow
Andras goal of Sustainability
Andras goal of Sustainability
As nuclear power assumes an increasingly important role in meeting the nation's requirements for electrical energy, the quantity of radioactive wastes will also increase. The wastes of primary concern -<br/>designated "high-level" and "alpha" wastes - contain radioactive nuclides that decay so slowly as to require that they be isolated from the biosphere for thousands of years.
Consideration of the technical feasibility of Yucca Mountain in Nevada as the site for a high-level nuclear<br/>waste repository has led to an intense debate regarding the economic, social, and political impacts of the<br/>repository.
Geologic repositories for radioactive waste are evolving<br/>from conceptualization to the development of specific<br/>designs. Estimates of long-term hazards must be based<br/>upon quantitative predictions of environmental releases<br/>over time periods of hundreds of thousands of years and<br/>longer.
A method is presented for determining the relative favorability<br/>of geologically complex areas for isolating high-level<br/>radioactive wastes. In applying the method to the northeastern region<br/>of the United States, seismieity and tectonic activity were the<br/>screening criteria used to divide the region into three areas of<br/>increasing seismotectonic risk. The following criteria, specified by<br/>the U.S.
The U.S. Nuclear Regulatory<br/>Commission (NRC) is proposing<br/>licensing criteria for disposal of spent<br/>nuclear fuel and high-level radioactive<br/>wastes in the proposed geologic<br/>repository at Yucca Mountain, Nevada.<br/>These criteria will address the<br/>performance of the repository system at<br/>Yucca Mountain, a system that must<br/>comprise both natural and engineered<br/>barriers.
Programs to manage and ultimately dispose of high-level radioactive wastes are unique from scientific and technological as well as socio-political aspects. From a scientific and technological perspective, high-level radioactive wastes remain potentially hazardous for geological time periods—many millennia—and scientific and technological programs must be put in place that result in a system that provides high confidence that the wastes will be isolated from the accessible environment for these many thousands of years.
The Nuclear Waste Management Organization (NWMO) is responsible for implementing Adaptive Phased Management (APM), Canada’s plan for the long-term care of the used nuclear fuel produced by Canada’s nuclear reactors.
Docket Number RW-RM-96-100, General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories-Notice of Proposed Rulemaking (NOPR)
In the past, criticality analysis of pressurized water reactor (PWR) fuel stored in racks and casks has assumed that the fuel is fresh with the maximum allowable initial enrichment. If credit is allowed for fuel burnup in the design of casks that are used in the transport of spent light water reactor fuel to a repository, the increase in payload can lead to a significant reduction in the cost of transport and a potential reduction in the risk to the public. A portion of the work has been performed at Oak Ridge National Laboratory (ORNL) in support of the U.S.
This report contributes to the InSOTEC research programme’s Work Package 1.1 that maps remaining socio-technical challenges to the implementation of geological disposal of radioactive waste across fourteen countries in the EU and North America (www.insotec.eu). The aim of this report is to provide an overview of the current situation of geological disposal of High Level radioactive Waste (HLW) and Spent Nuclear Fuel (SNF) in the USA.
In the course of producing electrical power in light water reactors (LWRs), the uranium
fuel accumulates fission products until the fission process is no longer efficient.for power
production. At that point the fuel is removed from the reactor and stored in water basins
to allow radioactivity to partially decay before further disposition. This fuel is referred
to as "spent fuel." Although spent fuel as it is discharged from a reactor is intensely
radioactive, it has been stored safely in moderate quantities for decades. Spent fuel could
The Nuclear Waste Policy Act of 1982, as amended (NWPA), establishes a process for the siting, construction and operation of one or more national repositories for permanent disposal of the Nation’s spent nuclear fuel (SNF) and high-level radioactive waste (HLW). In 1987, after the Department of Energy (the Department or DOE) had conducted studies of nine potential repository sites located throughout the United States, Congress amended the NWPA and selected the Yucca Mountain site in Nye County, Nevada as the only site for further study for the first national repository.
The Nuclear Waste Policy Act of 1982 (the Act), established a
step-by-step process for the siting of the nation's first repository for
high-level radioactive waste and spent fuel. The Act gave the Department of
Energy (DOE) the primary responsibility for conducting this siting process.
The first step in the process laid out in the Act was the development by
the DOE, with the concurrence of the Nuclear Regulatory Commission (NRC), of
general guidelines to be used by the Secretary of the DOE (the Secretary) in
Present regulatory practices provide as much burnup credit flexibility as can be currently
expected. Further progress is achievable by incorporating the negative reactivity effects of a
subset of neutron-absorbing fission-product isotopes, and by optimizing the procedural approach
for establishing the burnup characteristics of the spent fuel to be loaded in burnup-creditdesigned
storage and transportation systems. This report describes progress toward developing a
From 1998 to 2004, a series of critical experiments referred to as the fission product (FP) experimental program was performed at the Commissariat à l'Energie Atomique Valduc research facility. The experiments were designed by Institut de Radioprotection et de Sûreté Nucléaire (IRSN) and funded by AREVA NC and IRSN within the French program supporting development of a technical basis for burnup credit validation.
This report provides - a detailed description of the Austrian policy and the usual practices concerning the management of spent fuel of the Austrian research reactors and the management of radioactive waste (see Section B); - a detailed description of the Austrian legal regime concerning the management of spent fuel of the Austrian research reactors and the management of radioactive waste (see Section E).
In the United States, burnup credit has been used in the criticality safety evaluation for storage pools at
pressurized water reactors (PWRs) and considerable work has been performed to lay the foundation for use of
burnup credit in dry storage and transport cask applications and permanent disposal applications. Many of the
technical issues related to the basic physics phenomena and parameters of importance are similar in each of these
applications. However, the nuclear fuel cycle in the United States has never been fully integrated and the