Fast Reactor Fuel Reprocessing Development in the United States
Fast Reactor Fuel Reprocessing Development in the United States

Author:

Publisher:

Published: 1979

Total Pages: 53

ISBN-13:

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As a result of the reduced nuclear power demand and the growing concerns over the potential proliferation of sensitive nuclear materials, there has not been a necessity to make immediate decisions regarding near-term reprocessing and breeder reactor commercialization. Programs which formed the basic thrust of nuclear development in the early 1970's have already been adjusted: increased emphasis on problems of radioactive waste management; increased attention to nonproliferation objectives and subsequent reorientation of the overall fuel cycle and breeder programs; increased emphasis on a once-through light-water reactor technology; increased concern for a more detailed knowledge of the uranium resource base; reorientation of the uranium enrichment programs; and exploration of alternative fuel cycles (such as thorium) to minimize the use of plutonium. Nevertheless, major strategic decisions still loom over breeder commercialization, the breeder's requisite demand for reprocessing, and the future role of more proliferation-resistant nuclear technologies. The current program in the United States is organized to provide the necessary technology for the reprocessing of breeder fuels on a timetable that is consistent with the reactor development and demonstration program. Also addressed in this paper are the present day concerns of environmental protection, safety, nuclear material safeguards, and proliferation resistance. It is structured on the well-known Purex processing method but includes new efforts aimed at advanced and alternative fuels. At the present time, the program consists mainly of a generic effort that is planned to progress through an integrated equipment engineering demonstration to an eventual pilot-plant operation. Each of these facilities is viewed as a test bed for advanced and alternative processing steps to address the many significant technical and political issues. 16 figures.

Development of Fast Breeder Reactor Fuel Reprocessing Technology at the Power Reactor and Nuclear Fuel Development Corporation
Development of Fast Breeder Reactor Fuel Reprocessing Technology at the Power Reactor and Nuclear Fuel Development Corporation

Author:

Publisher:

Published: 1991

Total Pages: 9

ISBN-13:

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For the past two decades, a broad range of research development (R D) programs to establish fast breeder reactor (FBR) system and its associated fuel cycle technology have been pursued by the Power Reactor and Nuclear Fuel Development Corporation (PNC). Developmental activities for FBR fuel reprocessing technology have been primarily conducted at PNC Tokai Works where many important R D facilities for nuclear fuel cycle are located. These include cold and uranium tests for process equipment development in the Engineering Demonstration Facilities (EDF)-I and II, and laboratory-scale hot tests in the Chemical Processing Facility (CPF) where fuel dissolution and solvent extraction characteristics are being investigated with irradiated FBR fuel pins whose burn-up ranges up to 100,000 MWd/t. An extensive effort has also been made at EDF-III to develop advanced remote technology which enables to increase plant availability and to decrease radiation exposures to the workers in future reprocessing plants. The PNC and the United States Department of Energy (USDOE) entered into the joint collaboration in which the US shares the R Ds to support FBR fuel reprocessing program at the PNC. Several important R Ds on advanced process equipment such as a rotary dissolver and a centrifugal contactor system are in progress in a joint effort with the Oak Ridge National Laboratory (ORNL) Consolidated Fuel Reprocessing Program (CFRP). In order to facilitate hot testing on advanced processes and equipment, the design of a new engineering-scale hot test facility is now in progress aiming at the start of hot operation in late 90's. 31 refs., 2 tabs.

Nuclear Fuel Reprocessing And Waste Management
Nuclear Fuel Reprocessing And Waste Management

Author: Jinsuo Zhang

Publisher: World Scientific

Published: 2018-08-07

Total Pages: 308

ISBN-13: 9813271388

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The question of how to effectively, efficiently, and responsibly manage used nuclear fuels is a concern of major impediment in the light of today's increasing usage of nuclear power and development of advanced nuclear reactors. This book focuses on two significant areas of (used) nuclear fuel: the reprocessing technology, and waste disposal and management. The book covers the fundamental knowledge, the current state-of-the-art, and future research activities for each topic.This book provides readers with the fundamental knowledge behind of nuclear used fuel reprocessing and radioactive waste management, and their technical applications, and their requirements and practices; to make the readers aware of social, economic, and environmental concerns as well as technical research needs. The book covers two well-known and well-developed reprocessing technologies: aqueous reprocessing technology, and electrochemical pyroprocessing. On the subject of waste management, it covers the dry storage of used nuclear fuel, novel waste form design, and nuclear waste disposal.This book is a good guide for readers who want to understand, apply, or develop the technologies.