Proceedings of the Embedded Topical Meeting on DOE Spent Nuclear Fuel and Fissile Material Management, San Diego, California, June 4-8, 2000

Proceedings of the Embedded Topical Meeting on DOE Spent Nuclear Fuel and Fissile Material Management, San Diego, California, June 4-8, 2000 PDF Author:
Publisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 556

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Scientific Basis for Nuclear Waste Management XXV

Scientific Basis for Nuclear Waste Management XXV PDF Author: Materials Research Society. Meeting
Publisher:
ISBN: 9781558996496
Category : Technology & Engineering
Languages : en
Pages : 962

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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.

Uranium Dioxide

Uranium Dioxide PDF Author: J. Belle
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 744

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History, Development and Future of TRIGA Research Reactors

History, Development and Future of TRIGA Research Reactors PDF Author:
Publisher:
ISBN: 9789201281197
Category : Nuclear reactors
Languages : en
Pages : 131

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NUREG/CR.

NUREG/CR. PDF Author: U.S. Nuclear Regulatory Commission
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 140

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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.

Bringing Fusion to the U.S. Grid

Bringing Fusion to the U.S. Grid PDF Author: National Academies of Sciences Engineering and Medicine
Publisher:
ISBN: 9780309685382
Category :
Languages : en
Pages :

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Book Description
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.

Transportation of Used Fuel

Transportation of Used Fuel PDF Author:
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 2

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The 1996 Baseline Environmental Management Report: Report

The 1996 Baseline Environmental Management Report: Report PDF Author:
Publisher:
ISBN:
Category : Nuclear weapons plants
Languages : en
Pages :

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Optimized Core Design and Fuel Management of a Pebble-bed Type Nuclear Reactor

Optimized Core Design and Fuel Management of a Pebble-bed Type Nuclear Reactor PDF Author: Brian Boer
Publisher:
ISBN: 9781586039660
Category : Nuclear fuels
Languages : en
Pages : 0

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Book Description
The Very High Temperature Reactor (VHTR) has been selected by the international Generation IV research initiative as one of the six most promising nuclear reactor concepts that are expected to enter service in the second half of the 21st century. As one of the fourth generation nuclear reactors, the VHTR is characterized by high plant efficiency and a high fuel discharge burn-up level. More specifically, the (pebble-bed type) High Temperature Reactor (HTR) is known for its inherently safe characteristics, coming from a negative temperature reactivity feedback, a low power density and a large thermal inertia of the core.