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The heat capacity of a two-gram sample of neptunium dioxide was determined from 10 to 315 degrees K in an adiabatic calorimeter. At 298.16 degrees K, the molal entropy and enthalpy calculated from the heat capacity data are 19.19 (plus or minus) 0.1 cal degree (exp -1) and 2770 (plus or minus) 15 cal, respectively. A pronounced hump was found in the heat capacity curve of neptunium dioxide at 25.3 degrees K similar to that found by Long, Jones, and Gordon in uranium dioxide at 28.6 degrees K. This anomaly in the heat capacity is suggestive of a cooperative phenomenon and is attributed to the incidence of antiferromagnetism below the temperature of the maximum in the heat capacity. A calorimeter for gram-scale samples and a modification of the cryostat design of Ruehrwein and Huffman so as to employ only liquid helium and liquid nitrogen as refrigerants are described.
Unlike earlier books in this series, this review describes the selection of chemical thermodynamic data for species of two elements, neptunium and plutonium. Although this came about more by circumstance than design, it has allowed for a more consistent approach to chemical interpretation than might have occurred in two separate treatments. It has also drawn attention to cases where the available data do not show expected parallels, and where further work may be useful to confirm or refute apparent differences in the behaviour of neptunium and plutonium.
The low-temperature heat capacity behavior of PuO/sub 2/ was found to be anomalous and irreproducible, changing slightly after every one of seven liquid helium coolings. Data obtained from a second series of liquid helium coolings, made after refiring three of four original FuO/sub 2/ wafers in air, were consistent with the last run of the first series. The final low-temperature heat capacity vs temperature curve was more like that reported for ThO/sub 2/ than it was for similar curves reported for UO/sub 2/ and NpO/sub 2/. A least squares equation relating heat capacity and temperature is given for the low-temperature region. Values of heat capacity, entropy, and enthalpy are listed for several temperatures. (auth).
Advances in Nuclear Fuel Chemistry presents a high-level description of nuclear fuel chemistry based on the most recent research and advances. Dr. Markus H.A. Piro and his team of global, expert contributors cover all aspects of both the conventional uranium-based nuclear fuel cycle and non-conventional fuel cycles, including mining, refining, fabrication, and long-term storage, as well as emerging nuclear technologies, such as accident tolerant fuels and molten salt materials. Aimed at graduate students, researchers, academics and practicing engineers and regulators, this book will provide the reader with a single reference from which to learn the fundamentals of classical thermodynamics and radiochemistry. Consolidates the latest research on nuclear fuel chemistry into one comprehensive reference, covering all aspects of traditional and non-traditional nuclear fuel cycles Includes contributions from world-renowned experts from many countries representing government, industry and academia Covers a variety of fuel designs, including conventional uranium dioxide, mixed oxides, research reactor fuels, and molten salt fuels Written by experts with hands-on experience in the development of such designs
Progress in International Research on Thermodynamic and Transport Properties covers the proceedings of the 1962 Second Symposium by the same title, held at Purdue University and the Thermophysical Properties Research Center. This symposium brings together theoretical and experimental research works on the thermodynamic and transport properties of gases, liquids, and solids. This text is organized into nine parts encompassing 68 chapters that cover topics from thixotropy to molecular orbital calculations. The first three parts review papers on theoretical, experimental, and computational studies of the various aspects of thermodynamic properties. These parts discuss the principles of phase equilibria, throttling, volume heat capacity, steam, volumetric behavior, enthalpy, and density. The subsequent part highlights the theoretical evaluations of transport properties, such as viscosity, diffusion, and conductivity, as well as the transport processes. These topics are followed by surveys of the theories in intermolecular forces and their applications. Other parts consider the measurement of thermal conductivity, viscosity, and radiation. The final parts examine the properties of ionized gases and non-Newtonian fluids. This book will prove useful to mechanical and chemical engineers.
This volume is part of the series on "Chemical Thermodynamics", published under the aegis of the OECD Nuclear Energy Agency, and updates and expands the thermodynamic data on inorganic compounds and complexes of uranium, neptunium, plutonium, americium and technetium contained in the previous volumes of the series. A review team, composed of seven internationally recognized experts, has critically reviewed during five years all the scientific literature containing chemical thermodynamic information for the above mentioned systems that has appeared since the publication of the earlier volumes. The results of this critical review carried out following the Guidelines of the OECD NEA Thermochemical Database Project have been documented in the present volume, which contains new tables of selected values for formation and reaction thermodynamical properties and an extensive bibliography.