Author: Publisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 556
Book Description
Proceedings of the Embedded Topical Meeting on DOE Spent Nuclear Fuel and Fissile Material Management, San Diego, California, June 4-8, 2000
Author: Publisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 556
Book Description
Scientific Basis for Nuclear Waste Management XXV
Author: Materials Research Society. MeetingPublisher:
ISBN: 9781558996496
Category : Technology & Engineering
Languages : en
Pages : 962
Book Description
This volume opens with a keynote lecture by Rodney Ewing, member of the Board of Radioactive Waste Management of the National Research Council. Ewing summarizes 25 years of materials research in nuclear waste, emphasizing the progress that has been made and the challenges that still confront investigators and technologists in materials science and repository performance evaluation. The session is followed by one on container materials and engineered barriers, and includes a discussion on the corrosion performance expected for waste packages in the proposed high-level nuclear waste repository at Yucca Mountain, Nevada. Invited papers on performance assessment and repository studies for different national programs are also highlighted, with representation from the United States, Sweden, Japan, Belgium, Switzerland, Italy, and the United Kingdom. A large number of papers focus on the structure, properties, and degradation of various waste forms such as glasses, ceramics (mostly for plutonium immobilization), cements, and spent nuclear fuel. For the second consecutive time, the number of papers on ceramics far exceeds those on glass, which had been the dominant material discussed at this symposium over the prior 23 years. New studies on zirconates confirm the recently discovered high radiation damage-resistance of this material. Additional topics include: performance assessment in high-level waste disposal; performance assessment in low-level waste disposal; ceramic structure and corrosion; radiation effects in ceramics; glass structure and corrosion; spent fuel; spent fuel cladding and alternative waste forms; cements in radioactive waste immobilization; contaminant transport; natural analogs; and waste processing.
The Future of Nuclear Fuel Cycle
Author: Publisher:
ISBN: 9780982800843
Category : Energy policy
Languages : en
Pages : 237
Book Description
"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.
Design Lessons Drawn from the Decommissioning of Nuclear Facilities
Author: International Atomic Energy AgencyPublisher:
ISBN: 9789201132109
Category : Technology & Engineering
Languages : en
Pages : 0
Book Description
At a time when many older facilities are being decommissioned and many more are undergoing major retrofits to extend their lives, there is a wealth of information emerging to guide the design of new facilities. In this publication, the most important lessons learned in recent years are examined.
NUREG/CR.
Author: U.S. Nuclear Regulatory CommissionPublisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 164
Book Description
History, Development and Future of TRIGA Research Reactors
Author: Publisher:
ISBN: 9789201281197
Category : Nuclear reactors
Languages : en
Pages : 131
Book Description
Uranium Dioxide
Author: J. BellePublisher:
ISBN:
Category : Government publications
Languages : en
Pages : 744
Book Description
Advances in High Temperature Gas Cooled Reactor Fuel Technology
Author: International Atomic Energy AgencyPublisher:
ISBN: 9789201253101
Category : Business & Economics
Languages : en
Pages : 639
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.
Transportation of Used Fuel
Author: Preparing for Future Products of Biotechnology
Author: National Academies of Sciences, Engineering, and MedicinePublisher: National Academies Press
ISBN: 0309452058
Category : Science
Languages : en
Pages : 231
Book Description
Between 1973 and 2016, the ways to manipulate DNA to endow new characteristics in an organism (that is, biotechnology) have advanced, enabling the development of products that were not previously possible. What will the likely future products of biotechnology be over the next 5â€"10 years? What scientific capabilities, tools, and/or expertise may be needed by the regulatory agencies to ensure they make efficient and sound evaluations of the likely future products of biotechnology? Preparing for Future Products of Biotechnology analyzes the future landscape of biotechnology products and seeks to inform forthcoming policy making. This report identifies potential new risks and frameworks for risk assessment and areas in which the risks or lack of risks relating to the products of biotechnology are well understood.