Download or read book A Fast Reactor Transient Analysis Methodology for PCs written by Karl Otto Ott and published by . This book was released on 1991 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book A Fast Reactor Transient Analysis Methodology for PCs written by and published by . This book was released on 1991 with total page 69 pages. Available in PDF, EPUB and Kindle. Book excerpt: This Manual describes a PC program for LMR Transient Calculations, LTC, written in GW-BASIC. It calculates the power and temperature trajectories for unscrammed TOP and LOHS transients. The LOF transient treatment is not operational in the GW-BASIC program because of storage limitations. The corresponding mathematical model, which allows a rapid treatment of the kinetics and the various feedback effects, is described in Ref. 1. It is briefly reviewed in Sec. 1. The program structure is outlined in Sec. 2, followed by a more detailed description in Sec. 3. Computational details are presented in Appendix A.A complete listing of the GW-BASIC program is given in Appendix B. Appendix C shows input-echo and output for a TOP sample problem, and Appendix D is a Glossary of all quantities used in the LTC program. The limitations of the GW-BASIC storage (to about 60K) are removed if it is run within Quick-BASIC. This then allows the extension of this program to treat LOF transients. Running LTC in Quick-BASIC permits also larger Dimensions'' for TOP and LOHS transients.

Download or read book A Fast Reactor Transient Analysis Methodology for PCs Volume 2 LTC Program Manual written by and published by . This book was released on 1991 with total page 69 pages. Available in PDF, EPUB and Kindle. Book excerpt: This Manual describes a PC program for LMR Transient Calculations, LTC, written in GW-BASIC. It calculates the power and temperature trajectories for unscrammed TOP and LOHS transients. The LOF transient treatment is not operational in the GW-BASIC program because of storage limitations. The corresponding mathematical model, which allows a rapid treatment of the kinetics and the various feedback effects, is described in Ref. 1. It is briefly reviewed in Sec. 1. The program structure is outlined in Sec. 2, followed by a more detailed description in Sec. 3. Computational details are presented in Appendix A.A complete listing of the GW-BASIC program is given in Appendix B. Appendix C shows input-echo and output for a TOP sample problem, and Appendix D is a Glossary of all quantities used in the LTC program. The limitations of the GW-BASIC storage (to about 60K) are removed if it is run within Quick-BASIC. This then allows the extension of this program to treat LOF transients. Running LTC in Quick-BASIC permits also larger D̀̀imensions̀̀ for TOP and LOHS transients.

Download or read book A Fast Reactor Transient Analysis Methodology for PCs written by and published by . This book was released on 1992 with total page 57 pages. Available in PDF, EPUB and Kindle. Book excerpt: This manual augments the detailed manual of the GW-BASIC version of the LTC code for an application in QuickBASIC. As most of the GW-BASIC coding of this program for LMR Transient Calculations'' is compatible with QuickBASIC, this manual pertains primarily to the required changes, such as the handling of input and output. The considerable reduction in computation time achieved by this conversion is demonstrated for two sample problems, using a variety of hardware and execution options. The revised code is listed. Although the severe storage limitations of GW-BASIC no longer apply, the LOF transient path has not been completed in this QuickBASIC code. Its advantages are thus primarily in the much faster running time for TOP and LOHS transients. For the fastest PC hardware (486) and execution option the computation time is reduced by a factor of 124 compared to GW-BASIC on a 386/20.

Download or read book Neutronics Methods for Transient and Safety Analysis of Fast Reactors written by Marchetti, Marco and published by KIT Scientific Publishing. This book was released on 2017-03-02 with total page 164 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book A Faster Reactor Transient Analysis Methodology for PCs written by and published by . This book was released on 1991 with total page 43 pages. Available in PDF, EPUB and Kindle. Book excerpt: The simplified ANL model for LMR transient analysis, in which point kinetics as well as lumped descriptions of the heat transfer equations in all components are applied, is converted from a differential into an integral formulation. All differential balance equations are implicitly solved in terms of convolution integrals. The prompt jump approximation is applied as the strong negative feedback effectively keeps the net reactivity well below prompt critical. After implicit finite differencing of the convolution integrals, the kinetics equation assumes the form of a quadratic equation, the quadratic dynamics equation.'' This model forms the basis for GW-BASIC program, LTC, for LMR Transient Calculation program, which can effectively be run on a PC. The GW-BASIC version of the LTC program is described in detail in Volume 2 of this report.

Download or read book A Faster Reactor Transient Analysis Methodology for PCs Volume 1 The Computational Model written by and published by . This book was released on 1991 with total page 43 pages. Available in PDF, EPUB and Kindle. Book excerpt: The simplified ANL model for LMR transient analysis, in which point kinetics as well as lumped descriptions of the heat transfer equations in all components are applied, is converted from a differential into an integral formulation. All differential balance equations are implicitly solved in terms of convolution integrals. The prompt jump approximation is applied as the strong negative feedback effectively keeps the net reactivity well below prompt critical. After implicit finite differencing of the convolution integrals, the kinetics equation assumes the form of a quadratic equation, the ''quadratic dynamics equation.'' This model forms the basis for GW-BASIC program, LTC, for LMR Transient Calculation program, which can effectively be run on a PC. The GW-BASIC version of the LTC program is described in detail in Volume 2 of this report.

Download or read book Survey of Current Methods for Analysis of Fast Reactor Transients Including Meltdown written by A. H. Kazi and published by . This book was released on 1964 with total page 128 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Dynamic Simulation of Sodium Cooled Fast Reactors written by G Vaidyanathan and published by CRC Press. This book was released on 2022-11-18 with total page 289 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book provides the basis of simulating a nuclear plant, in understanding the knowledge of how such simulations help in assuring the safety of the plants, thereby protecting the public from accidents. It provides the reader with an in-depth knowledge about modeling the thermal and flow processes in a fast reactor and gives an idea about the different numerical solution methods. The text highlights the application of the simulation to typical sodium-cooled fast reactor. The book • Discusses mathematical modeling of the heat transfer process in a fast reactor cooled by sodium. • Compares different numerical techniques and brings out the best one for the solution of the models. • Provides a methodology of validation based on experiments. • Examines modeling and simulation aspects necessary for the safe design of a fast reactor. • Emphasizes plant dynamics aspects, which is important for relating the interaction between the components in the heat transport systems. • Discusses the application of the models to the design of a sodium-cooled fast reactor It will serve as an ideal reference text for senior undergraduate, graduate students, and academic researchers in the fields of nuclear engineering, mechanical engineering, and power cycle engineering.

Download or read book Fast Reactor Safety written by John Graham and published by Elsevier. This book was released on 2012-12-02 with total page 390 pages. Available in PDF, EPUB and Kindle. Book excerpt: Fast Reactor Safety deals with safety design criteria and methodology for fast reactors. Topics covered include safety evaluation methods, system disturbances, containment, and licensing. The characteristics of fast reactors, including heat ratings and coolants, are also discussed. Comprised of six chapters, this book opens with an overview of methods used to evaluate nuclear safety, along with neutron kinetics, thermal and feedback effects, and fault tree analysis. The reader is then introduced to possible system disturbances in relation to three distinct fast reactor systems: liquid-metal-cooled fast breeder reactors, gas-cooled fast breeder reactors, and steam-cooled fast breeder reactors. The next chapter looks at safety criteria that are set to define the design of a safe plant, together with the safety features that might be included. The remaining chapters focus on the particular problems of a sodium-cooled design; containment building and primary circuit and vessel containment; and licensing of the plant. This monograph is intended for graduates and undergraduates in nuclear engineering who are attending courses in reactor safety.

Download or read book Fast Spectrum Reactors written by Alan E. Waltar and published by Springer Science & Business Media. This book was released on 2011-09-28 with total page 717 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book is a complete update of the classic 1981 FAST BREEDER REACTORS textbook authored by Alan E. Waltar and Albert B. Reynolds, which , along with the Russian translation, served as a major reference book for fast reactors systems. Major updates include transmutation physics (a key technology to substantially ameliorate issues associated with the storage of high-level nuclear waste ), advances in fuels and materials technology (including metal fuels and cladding materials capable of high-temperature and high burnup), and new approaches to reactor safety (including passive safety technology), New chapters on gas-cooled and lead-cooled fast spectrum reactors are also included. Key international experts contributing to the text include Chaim Braun, (Stanford University) Ronald Omberg, (Pacific Northwest National Laboratory, Massimo Salvatores (CEA, France), Baldev Raj, (Indira Gandhi Center for Atomic Research, India) , John Sackett (Argonne National Laboratory), Kevan Weaver, (TerraPower Corporation) ,James Seinicki(Argonne National Laboratory). Russell Stachowski (General Electric), Toshikazu Takeda (University of Fukui, Japan), and Yoshitaka Chikazawa (Japan Atomic Energy Agency).

Download or read book Transient Analysis of the Primary System of a Liquid Metal cooled Fast Breeder Reactor Plant written by Grigore F. Pavlenco and published by . This book was released on 1976 with total page 740 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Kinetics Stability and Control written by R. L. Johnson and published by . This book was released on 1963 with total page 46 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Analysis of Transient Overpower Scenarios in Sodium Fast Reactors written by David Grabaskas and published by . This book was released on 2010 with total page 63 pages. Available in PDF, EPUB and Kindle. Book excerpt: Abstract: The objective of this research was the demonstration of a methodology to handle epistemic and aleatory uncertainties within an unprotected transient overpower (TOP) scenario in a sodium fast reactor. This study included a comparison of the risk of TOP scenarios to safety limits that are being considered by the U.S. Nuclear Regulatory Commission for future reactor designs. An analysis of the relative importance of uncertainties was also made. The results of this experiment demonstrated that the core damage frequency for an unprotected transient overpower scenario fell well below the proposed safety limits, even without taking credit for the reliability of the reactor protection system. The control rod driveline feedback and Doppler feedback mechanisms were found to be the most important epistemic uncertainties.

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 Fast Reactor Design with Enhanced Doppler Effect written by Maciej Zajaczkowski and published by . This book was released on 2020 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: In order to improve passive safety of Sodium-cooled Fast Reactors (SFR) in case of unprotected transients such as Unprotected Loss of Flow (ULOF) or Unprotected Transient Overpower (UTOP), The French Alternative Energies and Atomic Energy Commission proposed a CADOR concept - a new design of SFR core with enhanced Doppler effect. One of the most important design features is the addition of moderating materials inside fuel assemblies to decrease the average neutron energy by around 40%. The solution leads to roughly three times higher magnitude of Doppler effect due to the increase of resonance neutron population. On the other hand, the softened neutron spectrum changes other core properties. It increases the importance of low-energy neutron scattering and absorption. Moreover, the heterogeneous moderator placement in the assembly may cause an uneven reaction rate distribution and a risk of power peaks not observed in standard SFRs. To demonstrate the safety of CADOR design, it is essential to first evaluate the performance of calculation tools following a Verification, Validation and Uncertainty Quantification (VVUQ) - a process that must be applied to calculation codes and methods to show their reliability. The aforementioned changes in the neutron balance put into question the applicability of standard fast reactor neutronic calculation schemes to the case of CADOR. The purpose of this thesis, therefore, is to establish an accurate neutron transport calculation scheme, in line with VVUQ principles, that takes into account all relevant physical phenomena related to atypical properties of the CADOR core.A two-step calculation scheme of deterministic neutron transport code APOLLO3 was defined as a basis for the analysis. The CADOR cores with two different moderator types, Be and ZrH2, were used. The elements of the scheme and their possible improvements were studied through direct comparison with the reference Monte Carlo code TRIPOLI-4. The systematic biases of numerical models, such as: different spatial homogenization approaches or resonance upscattering treatment, different energy and spatial mesh definitions, were studied with respect to accuracy of multiplication factor, Doppler effect and reaction rates. The most important sources of uncertainties were identified and quantified. Finally, as a first estimation of the sensitivity of the multiphysics calculation scheme, the impact of the uncertainties on simulations UTOP and ULOF transients was evaluated via coupling with MACARENa, a calculation code for transient analysis in SFRs.The results indicate that the accuracy of calculation scheme can be improved by applying exact scattering treatment, notably in case of core with ZrH2 moderator where utilization of simplified scattering kernel leads to underestimation of Doppler effect of up to 5.2 %. With exact scattering treatment the global bias of the calculation scheme of APOLLO3 was estimated at approximately 500 pcm for core with Be moderator and 460 pcm for core with ZrH2 moderator. The biases in case of CADOR are of the same order of magnitude as for conventional SFR designs. By preserving more heterogeneous description of the fissile zone during homogenization process the global bias can be further reduced by 110-280 pcm depending on the studied level of heterogeneity; however this approach has a drawback of significantly higher computational complexity. The sensitivity analysis performed in MACARENa suggests that the uncertainties of neutronic calculations have minor impact on the progression of simulated transients. This work shows that the methods available in APOLLO3 provide a good accuracy of calculation of SFRs, even in case of less conventional designs. The low uncertainties of the calculation scheme indicate robustness of the numerical models used; the calculation scheme provides sufficient accuracy to be applied in fast reactor design and safety studies.

Download or read book Nuclear Science and Engineering written by and published by . This book was released on 1993 with total page 444 pages. Available in PDF, EPUB and Kindle. Book excerpt: