Ultra High Temperature Reactor Experiment Core Heat Transfer Calculations
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Ultra High Temperature Reactor Experiment (UHTREX) Hazard Report
Author | : Los Alamos Scientific Laboratory. K-Division |
Publisher | : |
Total Pages | : 168 |
Release | : 1962 |
Genre | : Nuclear reactors |
ISBN | : |
UHTREX utilizes a high-temperature, He-cooled, graphite moderated reactor employing unclad, refractory fuel elements. The reactor is designed to produce a maximum thermal power of 3 Mw and a maximum exit He temperature of 2400 deg F. The purpose of the experimert is to evaluate the advantages of the simple fuel against the disadvantages of the associated operation of a contaminated coolant loop. The mechanical and nuclear design of the reactor and related apparatus are described, discussed, and evaluated from the standpoint of hazards associated with conduct of the experiment. The building design and characteristics of the site are also examined from the same standpoint. The probable effects of operational errors and component failures are studied. The conseqnences of credible accidents are not considered to be catastrophic for either operating personnel or personnel in surrounding areas.
Physics of High-Temperature Reactors
Author | : Luigi Massimo |
Publisher | : Elsevier |
Total Pages | : 249 |
Release | : 2013-10-22 |
Genre | : Technology & Engineering |
ISBN | : 1483280284 |
Physics of High-Temperature Reactors focuses on the physics of high-temperature reactors (HTRs) and covers topics ranging from fuel cycles and refueling strategies to neutron cross-sections, transport and diffusion theory, and resonance absorption. Spectrum calculations and cross-section averaging are also discussed, along with the temperature coefficient and reactor control. Comprised of 16 chapters, this book begins with a general description of the HTR core as well as its performance limitations. The next chapter deals with general considerations about HTR physics, including quantities to be determined and optimized in the design of nuclear reactors. Potential scattering and resonance reactions between neutrons and atomic nuclei are then considered, together with basic aspects of transport and diffusion theory. Subsequent chapters explore methods for solving the diffusion equation; slowing-down and neutron thermalization in graphite; HTR core design, fuel management, and cost calculations; and core dynamics and accident analysis. The final chapter describes the sequence of reactor design calculations. This monograph is written primarily for students of HTR physics who are preparing to enter the field as well as technologists of other disciplines who are working on the system.
Heat Transfer Reactor Experiment No. 3
Author | : F. C. Linn |
Publisher | : |
Total Pages | : 210 |
Release | : 1962 |
Genre | : Nuclear propulsion |
ISBN | : |