Idaho National Laboratory Fuel Reprocessing Complex Historic American Engineering Record Report - ID-33-H
Idaho National Laboratory Fuel Reprocessing Complex Historic American Engineering Record Report - ID-33-H

Author: Brenda R. Pace

Publisher:

Published: 2006

Total Pages: 294

ISBN-13:

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For nearly four decades, the Fuel Reprocessing Complex (Buildings CPP-601, CPP-603, CPP-627, CPP-640) at the Idaho Chemical Processing Plant (ICPP) recovered usable uranium from spent reactor fuel. The facility was constantly evolving to process new types of spent nuclear fuel and would eventually process materials from nearly 100 different reactors. Research and test reactors located at the National Reactor Testing Station supplied a large proportion of the fuel load for the facility, along with nearly all of the fuel cores that had powered the United States Navy's fleet of nuclear submarines and surface ships. Fuels clad in aluminum, zirconium, stainless steel, and graphite were routinely processed at the plant. Custom processing capabilities were also developed through the years and a variety of valuable isotopes and inert gases were isolated and shipped to research laboratories across the country. AS ICPP scientists developed the facilities and the skills necessary to reprocess highly enriched fuels from so many different sources, they also came up with many general improvements and scientific advances in fuel reprocessing techniques and waste management as a whole. In 1992, when changing political tides and lowered demand for uranium caused the Department of Energy to halt all fuel reprocessing efforts across the country, approximately 31,432 kg of uranium had been successfully recovered at the Idaho Chemical Processing Plant. The four main buildings that housed the complex fuel reprocessing operation now await decontamination and demolition.

Viability of Inert Matrix Fuel in Reducing Plutonium Amounts in Reactors
Viability of Inert Matrix Fuel in Reducing Plutonium Amounts in Reactors

Author: International Atomic Energy Agency

Publisher: IAEA

Published: 2006

Total Pages: 100

ISBN-13:

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The reactors around the world have produced more than 2000 tonnes of plutonium, contained in spent fuel or as separated forms through reprocessing. Disposition of fissile materials has become a primary concern of nuclear non-proliferation efforts worldwide. There is a significant interest in IAEA Member States to develop proliferation resistant nuclear fuel cycles for incineration of plutonium such as inert matrix fuels (IMFs). This publication reviews the status of potential IMF candidates and describes several identified candidate materials for both fast and thermal reactors: MgO, ZrO2, SiC, Zr alloy, SiAl, ZrN; some of these have undergone test irradiations and post irradiation examination. Also discussed are modelling of IMF fuel performance and safety analysis. System studies have identified strategies for both implementation of IMF fuel as homogeneous or heterogeneous phases, as assemblies or core loadings and in existing reactors in the shorter term, as well as in new reactors in the longer term.

Internationalization of the Nuclear Fuel Cycle
Internationalization of the Nuclear Fuel Cycle

Author: Russian Academy of Sciences

Publisher: National Academies Press

Published: 2009-01-26

Total Pages: 172

ISBN-13: 0309185947

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The so-called nuclear renaissance has increased worldwide interest in nuclear power. This potential growth also has increased, in some quarters, concern that nonproliferation considerations are not being given sufficient attention. In particular, since introduction of many new power reactors will lead to requiring increased uranium enrichment services to provide the reactor fuel, the proliferation risk of adding enrichment facilities in countries that do not have them now led to proposals to provide the needed fuel without requiring indigenous enrichment facilities. Similar concerns exist for reprocessing facilities. Internationalization of the Nuclear Fuel Cycle summarizes key issues and analyses of the topic, offers some criteria for evaluating options, and makes findings and recommendations to help the United States, the Russian Federation, and the international community reduce proliferation and other risks, as nuclear power is used more widely. This book is intended for all those who are concerned about the need for assuring fuel for new reactors and at the same time limiting the spread of nuclear weapons. This audience includes the United States and Russia, other nations that currently supply nuclear material and technology, many other countries contemplating starting or growing nuclear power programs, and the international organizations that support the safe, secure functioning of the international nuclear fuel cycle, most prominently the International Atomic Energy Agency.

Tank Waste Retrieval, Processing, and On-site Disposal at Three Department of Energy Sites
Tank Waste Retrieval, Processing, and On-site Disposal at Three Department of Energy Sites

Author: National Research Council

Publisher: National Academies Press

Published: 2006-09-12

Total Pages: 214

ISBN-13: 0309180147

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DOE Tank Waste: How clean is clean enough? The U.S. Congress asked the National Academies to evaluate the Department of Energy's (DOE's) plans for cleaning up defense-related radioactive wastes stored in underground tanks at three sites: the Hanford Site in Washington State, the Savannah River Site in South Carolina, and the Idaho National Laboratory. DOE plans to remove the waste from the tanks, separate out high-level radioactive waste to be shipped to an off-site geological repository, and dispose of the remaining lower-activity waste onsite. The report concludes that DOE's overall plan is workable, but some important challenges must be overcomeâ€"including the removal of residual waste from some tanks, especially at Hanford and Savannah River. The report recommends that DOE pursue a more risk-informed, consistent, participatory, and transparent for making decisions about how much waste to retrieve from tanks and how much to dispose of onsite. The report offers several other detailed recommendations to improve the technical soundness of DOE's tank cleanup plans.

State-of-the-art Report on the Progress of Nuclear Fuel Cycle Chemistry
State-of-the-art Report on the Progress of Nuclear Fuel Cycle Chemistry

Author:

Publisher:

Published: 2018

Total Pages: 148

ISBN-13:

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The implementation of advanced nuclear systems requires that new technologies associated with the back end of the fuel cycle are developed. The separation of minor actinides from other fuel components is one of the advanced concepts being studied to help close the nuclear fuel cycle and to improve the long-term effects on the performance of geological repositories. Separating spent fuel elements and subsequently converting them through transmutation into short-lived nuclides should considerably reduce the longterm risks associated with nuclear power generation.

Thorium Fuel Cycle
Thorium Fuel Cycle

Author: International Atomic Energy Agency

Publisher:

Published: 2005

Total Pages: 120

ISBN-13:

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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 Future of Nuclear Fuel Cycle
The Future of Nuclear Fuel Cycle

Author:

Publisher:

Published: 2011

Total Pages: 237

ISBN-13: 9780982800843

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"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.

Plentiful Energy
Plentiful Energy

Author: Charles E. Till

Publisher: Createspace Independent Publishing Platform

Published: 2011

Total Pages: 0

ISBN-13: 9781466384606

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The Integral Fast Reactor (IFR) is a fast reactor system developed at Argonne National Laboratory in the decade 1984 to 1994. The IFR project developed the technology for a complete system; the reactor, the entire fuel cycle and the waste management technologies were all included in the development program. The reactor concept had important features and characteristics that were completely new and fuel cycle and waste management technologies that were entirely new developments. The reactor is a "fast" reactor - that is, the chain reaction is maintained by "fast" neutrons with high energy - which produces its own fuel. The IFR reactor and associated fuel cycle is a closed system. Electrical power is generated, new fissile fuel is produced to replace the fuel burned, its used fuel is processed for recycling by pyroprocessing - a new development - and waste is put in final form for disposal. All this is done on one self-sufficient site.The scale and duration of the project and its funding made it the largest nuclear energy R and D program of its day. Its purpose was the development of a long term massive new energy source, capable of meeting the nation's electrical energy needs in any amount, and for as long as it is needed, forever, if necessary. Safety, non-proliferation and waste toxicity properties were improved as well, these three the characteristics most commonly cited in opposition to nuclear power.Development proceeded from success to success. Most of the development had been done when the program was abruptly cancelled by the newly elected Clinton Administration. In his 1994 State of the Union address the president stated that "unnecessary programs in advanced reactor development will be terminated." The IFR was that program.This book gives the real story of the IFR, written by the two nuclear scientists who were most deeply involved in its conception, the development of its R and D program, and its management.Between the scientific and engineering papers and reports, and books on the IFR, and the non-technical and often impassioned dialogue that continues to this day on fast reactor technology, we felt there is room for a volume that, while accurate technically, is written in a manner accessible to the non-specialist and even to the non-technical reader who simply wants to know what this technology is.