Download or read book COMPILATION OF FAST REACTOR EXPERIMENTS written by and published by . This book was released on 1971 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Compilation of Fast Reactor Experiments written by and published by . This book was released on 1971 with total page 648 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book The Ongoing Impact of the U S Fast Reactor Integral Experiments Program written by and published by . This book was released on 2012 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The creation of a large database of integral fast reactor physics experiments advanced nuclear science and technology in ways that were unachievable by less capital intensive and operationally challenging approaches. They enabled the compilation of integral physics benchmark data, validated (or not) analytical methods, and provided assurance of future rector designs The integral experiments performed at Argonne National Laboratory (ANL) represent decades of research performed to support fast reactor design and our understanding of neutronics behavior and reactor physics measurements. Experiments began in 1955 with the Zero Power Reactor No. 3 (ZPR-3) and terminated with the Zero Power Physics Reactor (ZPPR, originally the Zero Power Plutonium Reactor) in 1990 at the former ANL-West site in Idaho, which is now part of the Idaho National Laboratory (INL). Two additional critical assemblies, ZPR-6 and ZPR-9, operated at the ANL-East site in Illinois. A total of 128 fast reactor assemblies were constructed with these facilities [1]. The infrastructure and measurement capabilities are too expensive to be replicated in the modern era, making the integral database invaluable as the world pushes ahead with development of liquid metal cooled reactors.

Download or read book Fast Reactor Type Fuel Pins Tested Under Loss of Flow Conditions written by and published by . This book was released on 1982 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book The Southwest Experimental Fast Oxide Reactor written by Karl P. Cohen and published by . This book was released on 1963 with total page 48 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Fast Reactor Type Fuel Pins Tested Under Loss of Flow Conditions written by H. Kwast and published by . This book was released on 1983 with total page 175 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Proceedings of the 1957 Fast Reactor Information Meeting Held at Chicago Ill November 20 21 1957 written by U.S. Atomic Energy Commission and published by . This book was released on 1957 with total page 296 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Techniques in Fast Reactor Critical Experiments written by W. G. Davey and published by Gordon & Breach Publishing Group. This book was released on 1970 with total page 344 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Fast Reactor Type Fuel Pins Tested Under Loss of Flow Conditions written by H. Kwast and published by . This book was released on 1982 with total page 302 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Reactor Technology written by and published by . This book was released on with total page 616 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Archival of the ZPPR 15B Physics Experiment written by and published by . This book was released on 2012 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This I-NERI collaboration between Argonne National Laboratory (ANL) and Korea Atomic Energy Research Institute (KAERI) began mid-year (April, 2010). This report summarizes the progress for year two of the proposed three-year collaboration to generate a physics validation database of integral experiments for metallic fueled fast reactor systems. The objective of the proposed project is to archive and evaluate the integral experiment data, analyze the experiments, and prepare detailed computational models to be used for validating the modern suites of fast reactor design analysis tools which are under development at ANL and KAERI. A series of mockup experiments for a 330 MWe Integral Fast Reactor (IFR) at ANL under the ZPPR-15 Program, also known as the IFR Benchmark Physics Test Program will be retrieved and analyzed in this project. The ZPPR-15 program was conducted in four phases. Each phase was marked by a particular composition of the reference assembly. In the first phase (15A), only plutonium, depleted uranium, stainless steel and sodium were included in this very clean physics assembly. This allowed examination of the effect of removing oxygen from the typical oxide-fueled sodium fast reactor. Zirconium was added in the second phase (15B). Additionally, 13 control rods and channels were added after the first phase. In the third phase (15C), roughly half of the core volume was fueled by enriched uranium to simulate a fast reactor transition composition. In the final phase (15D), the enriched uranium component was increased to 90%, simulating a near-beginning-of-life composition. In addition to criticality, control rod worths, reaction rate distribution, reactivity coefficients, gamma heating, neutron spectrum and kinetics, there were a number of measurements aimed at addressing special issues of safety, economics and metal fuel composition. The BFS-73-1 and BFS-75-1 experiments of KAERI carried out as the mockup experiment of KALIMER-150 at the Russian BFS-1 facility will also be compiled in this project. ANL will also participate in KAERI's transuranics (TRU) burner physics experiments which are now in progress at the BFS-2 facility to validate the physics performance of its metal-fueled TRU burner reactor design and design analysis tools. This burner reactor physics experiment data will be a valuable addition to the existing experiment database for breeder reactors. The principal outcomes of this project include (1) compiled sets of measured physics parameters and uncertainties of ZPPR-15 experiments and consistent sets of as-built Monte Carlo models and (2) compiled sets of measured physics parameters and uncertainties and consistent sets of as-built Monte Carlo models for BFS-73-1, BFS-75-1 and a mock-up of a 300 MWe-rated TRU burner reactor (BFS-76-1). Since both the U.S. and the Republic of Korea (ROK) are interested in a TRU burning option using metal-fueled fast reactors, it is mutually beneficial to generate the physics validation database of metal-fueled fast reactors using the ZPPR-15 experiments and the new TRU burner physics experiments at the BFS-2. On the current year task of generating the ZPPR-15B experimental database, the complete loading records for all of the ZPPR-15B configurations have been captured, verified and entered into a database for the generation of the as-built models. All ZPPR-15B drawer master identifications and logbooks have also been reviewed. Detailed as-built Monte Carlo models have been completed and analyzed for all of the twelve planned ZPPR-15B configurations, including the reference critical configuration, the sodium void worth measurements, and the worth measurements of the control rod and control rod positions. These experiments have been analyzed with continuous-energy Monte Carlo using both ENDF/B-V.2 and ENDF/B-VII.0. Criticality results with ENDF/B-VII.0 data are good, although exhibiting a slight underprediction (≈200 pcm) of k{sub eff} values. This is a slightly larger underprediction (≈100 pcm) than obtained with ENDF/B-VII.0 for ZPPR-15A. Sodium void worth results with ENDF/B-VII.0 data are generally within ≈5-10%. The positive worths of voiding the central zones are slightly underpredicted. Results with ENDF/B-VII.0 data are good (within ≈5%) for the control rod and control rod position measurements. Furthermore, the performance of the ENDF/B-VII.0 data for ZPPR-15B was consistent with the performance for ZPPR-15A, indicating good performance by the zirconium evaluation for these experiments. On the task of compiling TRU burner physics experiments at BFS, the as-built model of BFS-73-1 provided by KAERI has been reviewed and analyzed. Criticality results for BFS-73-1 are underpredicted by ≈340 pcm with both ENDF/B-VII.0 and -VII. 1 data. ANL has provided comments on a draft report of the BFS-76-1 measurements and discussions of the current BFS-76-1 experiments are on-going.

Download or read book Argonaut Reactor Databook written by W. J. Sturm and published by . This book was released on 1961 with total page 184 pages. Available in PDF, EPUB and Kindle. Book excerpt: This compilation has been prepared in order to provide a comprehensive unified summary of the principal elements of the design, operation and nuclear characteristics of the Argonaut reactor. Its primary content is made up of the theoretical and experimental evaluations of basic reactor parameters, both static and kinetic, which have been made to this date. The Databook includes also some practical information on the reactivity worths of fuel, moderator, and absorbers, as well as some data on radiation in the reactor vicinity.

Download or read book Status of Fast Reactor Research and Technology Development written by International Atomic Energy Agency and published by . This book was released on 2012 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: "Based on a recommendation from the Technical Working Group on Fast Reactors, this publication is a regular update of previous publications on fast reactor technology. The publication provides comprehensive and detailed information on the technology of fast neutron reactors. The focus is on practical issues that are useful to engineers, scientists, managers, university students and professors. The main issues of discussion are experience in design, construction, operation and decommissioning, various areas of research and development, engineering, safety and national strategies, and public acceptance of fast reactors. In the summary the reader will find national strategies, international initiatives on innovative (i.e. Generation IV) systems and an assessment of public acceptance as related to fast reactors."--Résumé de l'éditeur.

Download or read book Power Reactor Technology and Reactor Fuel Processing written by and published by . This book was released on 1967 with total page 1110 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Fast Breeder Reactor Program written by U.S. Atomic Energy Commission. Division of Reactor Development and published by . This book was released on 1960 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1975 with total page 844 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Liquid Metal Fast Breeder Reactors 1962 1971 written by U.S. Atomic Energy Commission and published by . This book was released on 1976 with total page 722 pages. Available in PDF, EPUB and Kindle. Book excerpt: