Proceedings Of The Embedded Topical Meeting On Doe Spent Nuclear Fuel And Fissile Material Management San Diego California June 4 8 2000
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Scientific Basis for Nuclear Waste Management XXV
Author | : Materials Research Society. Meeting |
Publisher | : |
Total Pages | : 962 |
Release | : 2002 |
Genre | : Technology & Engineering |
ISBN | : 9781558996496 |
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.
Viability of Inert Matrix Fuel in Reducing Plutonium Amounts in Reactors
Author | : International Atomic Energy Agency |
Publisher | : IAEA |
Total Pages | : 100 |
Release | : 2006 |
Genre | : Business & Economics |
ISBN | : |
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.
The Future of Nuclear Fuel Cycle
Author | : |
Publisher | : |
Total Pages | : 237 |
Release | : 2011 |
Genre | : Energy policy |
ISBN | : 9780982800843 |
"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.
History, Development and Future of TRIGA Research Reactors
Author | : |
Publisher | : |
Total Pages | : 131 |
Release | : 2016 |
Genre | : Nuclear reactors |
ISBN | : 9789201281197 |
Design Lessons Drawn from the Decommissioning of Nuclear Facilities
Author | : International Atomic Energy Agency |
Publisher | : |
Total Pages | : 0 |
Release | : 2011 |
Genre | : Technology & Engineering |
ISBN | : 9789201132109 |
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.
Uranium Dioxide
Author | : J. Belle |
Publisher | : |
Total Pages | : 744 |
Release | : 1961 |
Genre | : Government publications |
ISBN | : |
Bringing Fusion to the U.S. Grid
Author | : National Academies of Sciences Engineering and Medicine |
Publisher | : |
Total Pages | : |
Release | : 2021-11-17 |
Genre | : |
ISBN | : 9780309685382 |
Fusion energy offers the prospect of addressing the nation's energy needs and contributing to the transition to a low-carbon emission electrical generation infrastructure. Technology and research results from U.S. investments in the major fusion burning plasma experiment known as ITER, coupled with a strong foundation of research funded by the Department of Energy (DOE), position the United States to begin planning for its first fusion pilot plant. Strong interest from the private sector is an additional motivating factor, as the process of decarbonizing and modernizing the nation's electric infrastructure accelerates and companies seek to lead the way. At the request of DOE, Bringing Fusion to the U.S. Grid builds upon the work of the 2019 report Final Report of the Committee on a Strategic Plan for U.S. Burning Plasma Research to identify the key goals and innovations - independent of confinement concept - that are needed to support the development of a U.S. fusion pilot plant that can serve as a model for producing electricity at the lowest possible capital cost.
Advances in High Temperature Gas Cooled Reactor Fuel Technology
Author | : International Atomic Energy Agency |
Publisher | : |
Total Pages | : 639 |
Release | : 2012-06 |
Genre | : Business & Economics |
ISBN | : 9789201253101 |
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.