Considerations on the Media for Decay Storage of Fuel Elements

Considerations on the Media for Decay Storage of Fuel Elements PDF Author: W. K. Winegardner
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 48

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Book Description
This report was prepared in response to a Fast Flux Test Facility (FFTF) Division request for information and recommendations concerning the decay storage of irradiated fuel elements. The report first summarizes information concerning irradiated fuel element storage techniques. This summary is followed by a discussion of information related to fuel cladding corrosion problems that conceivably could result from decay storage after in-core exposure. Finally, all of the information, obtained primarily by literature review, is used as the basis for recommendations concerning storage media. The work was prompted by concern over possible loss of fuel element cladding integrity during decay storage in air or water. The concern ranges from effects that could hinder fuel examination to those that could result in local regions of cladding penetration or even failure while handling fuel. This report is primarily related tot he latter type of effect, since the facility is viewed simply as a cell or basin where fuel elements can safely be stored prior to chemical processing.

Nuclear Science Abstracts

Nuclear Science Abstracts PDF Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 882

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Book Description


Nuclear Science Abstracts

Nuclear Science Abstracts PDF Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1004

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Book Description


Technical Publications of Battelle-Northwest During 1968

Technical Publications of Battelle-Northwest During 1968 PDF Author:
Publisher:
ISBN:
Category : Research
Languages : en
Pages : 60

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Book Description
This report is one of an annual series and announces formal research and development reports and technical articles published during 1968 by Battelle-Northwest. The reports were issued in accordance with the AEC Standard Distribution Lists for Scientific and Technical Reports (AEC Documents TID-4500 and M-3679). The unclassified reports are generally available from the Clearinghouse for Federal Scientific and Technical Information, U.S. Department of Commerce, Springfield, Virginia 22151. Classified reports are available, with proper literature access, from the AEC's Division of Technical Information Extension (DTIE), P.O. Box 62, Oak Ridge Tennessee 37830. The reports and articles are grouped by broad subject categories and arranged alphabetically by author within each category. An author index and report number index are also included. Other reports in this series are BNWL-218, BNWL-387, and BNWL-700.

Strategy and Methodology for Radioactive Waste Characterization

Strategy and Methodology for Radioactive Waste Characterization PDF Author: International Atomic Energy Agency
Publisher: IAEA
ISBN:
Category : Business & Economics
Languages : en
Pages : 188

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Book Description
Over the past decade significant progress has been achieved in the development of waste characterization and control procedures and equipment as a direct response to ever-increasing requirements for quality and reliability of information on waste characteristics. Failure in control procedures at any step can have important, adverse consequences and may result in producing waste packages which are not compliant with the waste acceptance criteria for disposal, thereby adversely impacting the repository. The information and guidance included in this publication corresponds to recent achievements and reflects the optimum approaches, thereby reducing the potential for error and enhancing the quality of the end product. -- Publisher's description.

TID.

TID. PDF Author:
Publisher:
ISBN:
Category : Energy development
Languages : en
Pages : 720

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Book Description


Going the Distance?

Going the Distance? PDF Author: National Research Council
Publisher: National Academies Press
ISBN: 0309100046
Category : Science
Languages : en
Pages : 355

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Book Description
This new report from the National Research Council's Nuclear and Radiation Studies Board (NRSB) and the Transportation Research Board reviews the risks and technical and societal concerns for the transport of spent nuclear fuel and high-level radioactive waste in the United States. Shipments are expected to increase as the U.S. Department of Energy opens a repository for spent fuel and high-level waste at Yucca Mountain, and the commercial nuclear industry considers constructing a facility in Utah for temporary storage of spent fuel from some of its nuclear waste plants. The report concludes that there are no fundamental technical barriers to the safe transport of spent nuclear fuel and high-level radioactive and the radiological risks of transport are well understood and generally low. However, there are a number of challenges that must be addressed before large-quantity shipping programs can be implemented successfully. Among these are managing "social" risks. The report does not provide an examination of the security of shipments against malevolent acts but recommends that such an examination be carried out.

Advances in High Temperature Gas Cooled Reactor Fuel Technology

Advances in High Temperature Gas Cooled Reactor Fuel Technology PDF Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201253101
Category : Business & Economics
Languages : en
Pages : 639

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Book Description
This publication reports on the results of a coordinated research project on advances in high temperature gas cooled reactor (HTGR) fuel technology and describes the findings of research activities on coated particle developments. These comprise two specific benchmark exercises with the application of HTGR fuel performance and fission product release codes, which helped compare the quality and validity of the computer models against experimental data. The project participants also examined techniques for fuel characterization and advanced quality assessment/quality control. The key exercise included a round-robin experimental study on the measurements of fuel kernel and particle coating properties of recent Korean, South African and US coated particle productions applying the respective qualification measures of each participating Member State. The summary report documents the results and conclusions achieved by the project and underlines the added value to contemporary knowledge on HTGR fuel.

Disposition of High-Level Waste and Spent Nuclear Fuel

Disposition of High-Level Waste and Spent Nuclear Fuel PDF Author: National Research Council
Publisher: National Academies Press
ISBN: 0309073170
Category : Science
Languages : en
Pages : 215

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Book Description
Focused attention by world leaders is needed to address the substantial challenges posed by disposal of spent nuclear fuel from reactors and high-level radioactive waste from processing such fuel. The biggest challenges in achieving safe and secure storage and permanent waste disposal are societal, although technical challenges remain. Disposition of radioactive wastes in a deep geological repository is a sound approach as long as it progresses through a stepwise decision-making process that takes advantage of technical advances, public participation, and international cooperation. Written for concerned citizens as well as policymakers, this book was sponsored by the U.S. Department of Energy, U.S. Nuclear Regulatory Commission, and waste management organizations in eight other countries.

Handling and Processing of Radioactive Waste from Nuclear Applications

Handling and Processing of Radioactive Waste from Nuclear Applications PDF Author: International Atomic Energy Agency
Publisher:
ISBN:
Category : Business & Economics
Languages : en
Pages : 164

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Book Description
Provides detailed information on the handling, processing and storage techniques most widely used and recommended for waste from non-fuel-cycle activities. The report was designed to meet the needs of developing countries by focusing on the most simple, affordable and reliable techniques and discussing their advantages and limitations.