Download or read book The Use of Reduced Delayed Neutron Group Representations in Nuclear Reactor Simulation written by R. W. Albrecht and published by . This book was released on 1964 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Reduced Delayed Neutron Group Representations written by R. E. Skinner and published by . This book was released on 1959 with total page 40 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Delayed Neutron Reduced Groups by Least Squares written by Thomas E. Springer and published by . This book was released on 1964 with total page 42 pages. Available in PDF, EPUB and Kindle. Book excerpt:
- Author : Nguyen van Minh
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- Release : 1973
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- Pages : 0 pages
Solution for a Nonlinear Nuclear Reactor with Negative Prompt Feedback and One Group Delayed Neutron
Download or read book Solution for a Nonlinear Nuclear Reactor with Negative Prompt Feedback and One Group Delayed Neutron written by Nguyen van Minh and published by . This book was released on 1973 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: The nonlinear space time neutron flux equation with negative prompt feedback and one-group delayed neutron is reduced by the use of a nonlinear transformation to a partial differential equation, in which the nonlinear term represents a small perturbation. The general procedure of solution for the resulting weakly nonlinear initial-boundary-value problem is then established by means of the method of successive approximation. Convergence of the analytical solution is also discussed. The solutions to a slab reactor core and a cylindrical reactor core are investigated here. Asymptotic stable equilibrium states are derived from each of these solutions. The present results are consistent with those obtained from previous stability analysis for the generalized buckling K greater or less than (Mu sub 0, sup 2), the lowest eigenvalue of the associated linear Helmholtz equation. (Author).
Download or read book Power Reactor Technology written by and published by . This book was released on 1963 with total page 1084 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book A Statistical Determination of the Reduced Prompt Neutron Generation Time lambda beta in the SPERT IV Reactor written by Roger Lee Johnson and published by . This book was released on 1963 with total page 66 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Power Reactor Technology and Reactor Fuel Processing written by and published by . This book was released on 1964 with total page 548 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Evaluation and Application of Delayed Neutron Precursor Data written by Michaele Clarice Brady and published by . This book was released on 1988 with total page 564 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Proceedings of Conference on the Effective Use of Computers in Nuclear Industry Knoxville Tennessee April 21 23 1969 written by and published by . This book was released on 1969 with total page 704 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 1976 with total page 612 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Reports Received by Division of Technical Information Extension written by U.S. Atomic Energy Commission. Division of Technical Information and published by . This book was released on with total page 824 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book New Evaluation of Delayed neutron Data and Associated Covariances written by Daniela Foligno and published by . This book was released on 2019 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: In the context of nuclear reactor physics, one of the main issues is the control of the chain reaction. After a fission event has occurred, around three prompt neutrons are immediately emitted. Luckily, a small fraction of neutrons - less than 1% - appears with a certain delay with respect to the fission event. Delayed neutrons (DN) are an easy way out from the uncontrollable prompt-neutron driven chain reaction because they slow down the response of the reactor to a change in reactivity. Quantifying the fraction of such neutrons as well as their kinetic behavior is essential to design a safe reactor. The main consequence of a lack of accurate DN data is the conservatism in the design of a reactor. Nowadays, the discrepancy between the reactivity simulated using different international databases, rises up to 16% for LWRs, and the uncertainties associated with the recommended parameters are still too large for the needs of the industry. The DN parameters are generally estimated through a calculation or an integral measurement. This Ph.D. aims at producing a new set of DN parameters by performing both calculations and measurements, and by exploiting the two through the Bayesian inference, with the aim of reducing the uncertainties and creating the associated covariance matrices.The results for 235U, together with the calculated values for 238U, have been tested in three benchmarks, giving satisfying solutions with respect to the effective delayed neutron fraction. The main achievement of this work is the great improvement in the predicted reactivity, especially for negative periods, which is accompanied by an extremely good precision, never exceeding 2.2%.
Download or read book A New Experimental Design and Method for Improved Delayed Neutron Data of Group Abundances written by Heejun Chung and published by . This book was released on 2014 with total page 150 pages. Available in PDF, EPUB and Kindle. Book excerpt: The nuclear data on the physics of delayed neutrons coming from fission events are of key importance in reactor kinetics and safeguards applications. The accuracy of reactor kinetics calculations, reactor physics validation studies and techniques for non-destructive assay of special nuclear material are all limited by the quality of these data. The uncertainties on the delayed neutron group abundances of the longest-lived delayed neutron groups are particularly large - up to 13 % for thermal fissions of 235U, 16 % for fast fissions of 238U, and 38 % for fast fissions of 239Pu [1]. There are also several competing data sets with significant variation in values. Recent work indicates that these already large uncertainties are underestimated due to numerical instabilities in the parametric fitting methods [2]. A novel approach to experimentally measure delayed neutron group yields has been proposed by Jordan and Perret [3]. This approach combines gamma-ray scanning and delayed neutron fission rate measurement techniques. With two independent estimates of the same fission rate, a higher uncertainty delayed neutron parameters can be linked to lower uncertainty delayed gamma parameters. An experimental apparatus implementing these techniques has been designed, optimized, and built. The apparatus consists of a D-D neutron generator, a detector bundle, a sample handler, and related electronics.
Download or read book Dynamics and Control of Nuclear Reactors written by Thomas W. Kerlin and published by Academic Press. This book was released on 2019-10-05 with total page 402 pages. Available in PDF, EPUB and Kindle. Book excerpt: Dynamics and Control of Nuclear Reactors presents the latest knowledge and research in reactor dynamics, control and instrumentation; important factors in ensuring the safe and economic operation of nuclear power plants. This book provides current and future engineers with a single resource containing all relevant information, including detailed treatments on the modeling, simulation, operational features and dynamic characteristics of pressurized light-water reactors, boiling light-water reactors, pressurized heavy-water reactors and molten-salt reactors. It also provides pertinent, but less detailed information on small modular reactors, sodium fast reactors, and gas-cooled reactors. Provides case studies and examples to demonstrate learning through problem solving, including an analysis of accidents at Three Mile Island, Chernobyl and Fukushima Daiichi Includes MATLAB codes to enable the reader to apply the knowledge gained to their own projects and research Features examples and problems that illustrate the principles of dynamic analysis as well as the mathematical tools necessary to understand and apply the analysis Publishers Note: Table 3.1 has been revised and will be included in future printings of the book with the following data: Group Decay Constant, li (sec-1) Delayed Neutron Fraction (bi) 1 0.0124 0.000221 2 0.0305 0.001467 3 0.111 0.001313 4 0.301 0.002647 5 1.14 0.000771 6 3.01 0.000281 Total delayed neutron fraction: 0.0067
Download or read book Neutron Fluctuations written by Imre Pazsit and published by Elsevier. This book was released on 2007-10-05 with total page 359 pages. Available in PDF, EPUB and Kindle. Book excerpt: The transport of neutrons in a multiplying system is an area of branching processes with a clear formalism. Neutron Fluctuations presents an account of the mathematical tools used in describing branching processes, which are then used to derive a large number of properties of the neutron distribution in multiplying systems with or without an external source. In the second part of the book, the theory is applied to the description of the neutron fluctuations in nuclear reactor cores as well as in small samples of fissile material. The question of how to extract information about the system under study is discussed. In particular the measurement of the reactivity of subcritical cores, driven with various Poisson and non-Poisson (pulsed) sources, and the identification of fissile material samples, is illustrated. The book gives pragmatic information for those planning and executing and evaluating experiments on such systems. Gives a complete treatise of the mathematics of branching particle processes, and in particular neutron fluctuations, in a self-contained manner The first monograph containing the theory and application of neutron fluctuations in low power ADS (spallation and pulsed sources) Suitable as a tutorial and handbook/reference book for scientists and graduate students One of the authors is the founder of the mathematical theory of neutron fluctuations in zero power systems
Download or read book Hanford Formal Research and Development Reports written by and published by . This book was released on 1964 with total page 44 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Progress in Instrumentation Research and Development written by D. C Worlton and published by . This book was released on 1964 with total page 60 pages. Available in PDF, EPUB and Kindle. Book excerpt: