"In this analysis we have presented a method that provides insight into future fuel cycle alternatives by clarifying the complexity of choosing an appropriate fuel cycle in the context of the distribution of burdens and benefits between generations. The current nuclear power deployment practices, together with three future fuel cycles were assessed."--Page 227.
The Nuclear Threat Initiative and the Center for Strategic and International Studies joined to launch the New Approaches to the Fuel Cycle project. This project sought to build consensus on common goals, address practical challenges, and engage a spectrum of actors that influence policymaking regarding the nuclear fuel cycle. The project also tackled one of the toughest issues—spent nuclear fuel and high level waste—to see if solutions there might offer incentives to states on the front end of the nuclear fuel cycle and address the inherent inertia and concerns about additional burdens and restrictions that have stalled past efforts to improve the robustness of the nonproliferation regime. This report presents the group’s conclusions that a best-practices approach to the nuclear fuel cycle can achieve these objectives and offer a path to a more secure and sustainable nuclear landscape.
Provides a critical review of the thorium fuel cycle: potential benefits and challenges in the thorium fuel cycle, mainly based on the latest developments at the front end of the fuel cycle, applying thorium fuel cycle options, and at the back end of the thorium fuel cycle.
The Nuclear Fuel Cycle Simulation System (VISTA) is a simulation system which estimates long term nuclear fuel cycle material and service requirements as well as the material arising from the operation of nuclear fuel cycle facilities and nuclear power reactors. It is a scenario based simulation tool which can model several nuclear fuel cycle options including existing nuclear power reactor types and future possible reactor types. The past operations of the power reactors and fuel cycle facilities can be modelled in the system, in order to estimate the current amount of spent fuel stored or total Pu in stored spent fuel. It can also accept future projections for nuclear power and other scenario parameters in order to predict future fuel cycle material requirements.The model has been designed to be an optimum mixture of simplicity, speed and accuracy. It does not require too many input parameters if the purpose is just to compare the requirements for selected scenarios. Furthermore, the accuracy of the system can be improved by introducing more detailed and correct sets of input parameters.
The worldwide expansion of nuclear energy has been accompanied by concerns about nuclear weapons proliferation. If sited in states that do not possess nuclear weapons technology, some civilian nuclear technologies could provide a route for states or other organizations to acquire nuclear weapons. Metrics for assessing the resistance of a nuclear technology to diversion for non-peaceful uses-proliferation resistance-have been developed, but at present there is no clear consensus on whether and how these metrics are useful to policy decision makers. In 2011, the U.S. Department of Energy asked the National Academies to convene a public workshop addressing the capability of current and potential methodologies for assessing host state proliferation risk and resistance to meet the needs of decision makers. Proliferation Risk in Nuclear Fuel Cycles is a summary of presentations and discussions that transpired at the workshop-held on August 1-2, 2011-prepared by a designated rapporteur following the workshop. It does not provide findings and recommendations or represent a consensus reached by the symposium participants or the workshop planning committee. However, several themes emerged through the workshop: nonproliferation and new technologies, separate policy and technical cultures, value of proliferation resistance analysis, usefulness of social science approaches. The workshop was organized as part of a larger project undertaken by the NRC, the next phase of which (following the workshop) will be a consensus study on improving the assessment of proliferation risks associated with nuclear fuel cycles. This study will culminate in a report prepared by a committee of experts with expertise in risk assessment and communication, proliferation metrics and research, nuclear fuel cycle facility design and engineering, international nuclear nonproliferation and national security policy, and nuclear weapons design. This report is planned for completion in the spring of 2013.
Drawing on the authors' extensive experience in the processing and disposal of waste, An Introduction to Nuclear Waste Immobilisation, Second Edition examines the gamut of nuclear waste issues from the natural level of radionuclides in the environment to geological disposal of waste-forms and their long-term behavior. It covers all-important aspects of processing and immobilization, including nuclear decay, regulations, new technologies and methods. Significant focus is given to the analysis of the various matrices used, especially cement and glass, with further discussion of other matrices such as bitumen. The final chapter concentrates on the performance assessment of immobilizing materials and safety of disposal, providing a full range of the resources needed to understand and correctly immobilize nuclear waste.
The nuclear fuel cycle is characterised by the wide range of scientific disciplines and technologies it employs. The development of ever more integrated processes across the many stages of the nuclear fuel cycle therefore confronts plant manufacturers and operators with formidable challenges. Nuclear fuel cycle science and engineering describes both the key features of the complete nuclear fuel cycle and the wealth of recent research in this important field.Part one provides an introduction to the nuclear fuel cycle. Radiological protection, security and public acceptance of nuclear technology are considered, along with the economics of nuclear power. Part two goes on to explore materials mining, enrichment, fuel element design and fabrication for the uranium and thorium nuclear fuel cycle. The impact of nuclear reactor design and operation on fuel element irradiation is the focus of part three, including water and gas-cooled reactors, along with CANDU and Generation IV designs. Finally, part four reviews spent nuclear fuel and radioactive waste management.With its distinguished editor and international team of expert contributors, Nuclear fuel cycle science and engineering provides an important review for all those involved in the design, fabrication, use and disposal of nuclear fuels as well as regulatory bodies and researchers in this field. - Provides a comprehensive and holistic review of the complete nuclear fuel cycle - Reviews the issues presented by the nuclear fuel cycle, including radiological protection and security, public acceptance and economic analysis - Discusses issues at the front-end of the fuel cycle, including uranium and thorium mining, enrichment and fuel design and fabrication