Download or read book Thermophysical Properties of Thorium and Uranium Systems for Use in Reactor Safety Analysis written by and published by . This book was released on 1977 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The data compilation is intended to serve as a preliminary set of thermophysical property values for use in reactor safety analyses of the Th--233U reactor concept. The properties covered include mp, bp, enthalpy, heats of vaporization and fusion, heat capacity, thermal conductivity, density, thermal expansion, emissivity, viscosity, etc. The systems covered are Th, Th0.9U0.1, U, ThO2, Th0.9U0.1O2, UO2, U0. Pu0.2O2, ThC, Th0.9U0.1C, UC, U0.8Pu0.2C, ThC2, Th0.9U0.1C2, and UC2. 5 figures, 10 tables, 150 references. (DLC).

Download or read book Energy Research Abstracts written by and published by . This book was released on 1988 with total page 496 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book NUREG CR written by U.S. Nuclear Regulatory Commission and published by . This book was released on 1980 with total page 180 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Fast Breeder Reactors written by Alan Edward Waltar and published by Alan E. Waltar. This book was released on 1981 with total page 877 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Molten Salt Reactors and Thorium Energy written by Thomas James Dolan and published by Elsevier. This book was released on 2024-01-25 with total page 1068 pages. Available in PDF, EPUB and Kindle. Book excerpt: Molten Salt Reactors and Thorium Energy, Second Edition is a fully updated comprehensive reference on the latest advances in MSR research and technology. Building on the successful first edition, Tom Dolan and the team of experts have fully updated the content to reflect the impressive advances from the last 5 years, ensuring this book continues to be the go-to reference on the topic. This new edition covers progress made in MSR design, details innovative experiments, and includes molten salt data, corrosion studies and deployment plans. The successful case studies section of the first edition have been removed, expanded, and fully updated, and are now published in a companion title called Global Case Studies on Molten Salt Reactors. Readers will gain a deep understanding of the advantages and challenges of MSR development and thorium fuel use, as well as step-by-step guidance on the latest in MSR reactor design. Each chapter provides a clear introduction, covers technical issues and includes examples and conclusions, while promoting the sustainability benefits throughout. - A fully updated comprehensive handbook on Molten Salt Reactors and Thorium Energy, written by a team of global experts - Covers MSR applications, technical issues, reactor types and reactor designs - Includes 3 brand new chapters which reflect the latest advances in research and technology since the first edition published - Presents case studies on molten salt reactors which aid in the transition to net zero by providing abundant clean, safe energy to complement wind and solar powe

Download or read book Thorium Fuel Cycle written by International Atomic Energy Agency and published by . This book was released on 2005 with total page 120 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1975 with total page 640 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book The Use of Thorium in Nuclear Power Reactors written by and published by . This book was released on 1969 with total page 160 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Advanced Reactor Accident Delineation Assessment written by Ivan Catton and published by . This book was released on 1980 with total page 180 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Isothermal Temperature Coefficient for the SRE with Thorium uranium Fuel written by R. A. Lewis and published by . This book was released on 1961 with total page 30 pages. Available in PDF, EPUB and Kindle. Book excerpt: A measurement of the isothermal temperature coefficient of reactivity was made in December 1960 for the Th-U fuel loading of the SRE. It was found to be 0.33 cents/F° at 350°F and 0.12 cents/F° at 710°F. The uncertainty in the results is approximately ± 0.01 cents/F°.

Download or read book Nuclear Safety Research Index Fast reactors written by OECD Nuclear Energy Agency. Committee on the Safety of Nuclear Installations and published by . This book was released on 1979 with total page 700 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1971 with total page 280 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book ERDA Energy Research Abstracts written by United States. Energy Research and Development Administration and published by . This book was released on 1977 with total page 818 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Thermophysical Properties Research Literature Retrieval Guide 1900 1980 written by J. F. Chaney and published by Springer. This book was released on 1982 with total page 448 pages. Available in PDF, EPUB and Kindle. Book excerpt: See AD-A135 225 for Abstract.

Download or read book Monthly Catalog of United States Government Publications written by United States. Superintendent of Documents and published by . This book was released on 1979 with total page 1250 pages. Available in PDF, EPUB and Kindle. Book excerpt: February issue includes Appendix entitled Directory of United States Government periodicals and subscription publications; September issue includes List of depository libraries; June and December issues include semiannual index

Download or read book Monthly Catalogue United States Public Documents written by and published by . This book was released on 1979 with total page 1256 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Analysis of Key Safety Metrics of Thorium Utilization in LWRs written by and published by . This book was released on 2016 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt: Here, thorium has great potential to stretch nuclear fuel reserves because of its natural abundance and because it is possible to breed the 232Th isotope into a fissile fuel (233U). Various scenarios exist for utilization of thorium in the nuclear fuel cycle, including use in different nuclear reactor types (e.g., light water, high-temperature gas-cooled, fast spectrum sodium, and molten salt reactors), along with use in advanced accelerator-driven systems and even in fission-fusion hybrid systems. The most likely near-term application of thorium in the United States is in currently operating light water reactors (LWRs). This use is primarily based on concepts that mix thorium with uranium (UO2 + ThO2) or that add fertile thorium (ThO2) fuel pins to typical LWR fuel assemblies. Utilization of mixed fuel assemblies (PuO2 + ThO2) is also possible. The addition of thorium to currently operating LWRs would result in a number of different phenomenological impacts to the nuclear fuel. Thorium and its irradiation products have different nuclear characteristics from those of uranium and its irradiation products. ThO2, alone or mixed with UO2 fuel, leads to different chemical and physical properties of the fuel. These key reactor safety-related issues have been studied at Oak Ridge National Laboratory and documented in "Safety and Regulatory Issues of the Thorium Fuel Cycle" (NUREG/CR-7176, U.S. Nuclear Regulatory Commission, 2014). Various reactor analyses were performed using the SCALE code system for comparison of key performance parameters of both ThO2 + UO2 and ThO2 + PuO2 against those of UO2 and typical UO2 + PuO2 mixed oxide fuels, including reactivity coefficients and power sharing between surrounding UO2 assemblies and the assembly of interest. The decay heat and radiological source terms for spent fuel after its discharge from the reactor are also presented. Based on this evaluation, potential impacts on safety requirements and identification of knowledge gaps that require additional analysis or research to develop a technical basis for the licensing of thorium fuel are identified.