Download or read book Calculation of Reactor Transients written by H. Dean Brown and published by . This book was released on 1960 with total page 56 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nodal Methods for Calculating Nuclear Reactor Transients Control Rod Patterns and Fuel Pin Powers written by Byung-Oh Cho and published by . This book was released on 1990 with total page 322 pages. Available in PDF, EPUB and Kindle. Book excerpt: Nodal methods which are used to calculate reactor transients, control rod patterns, and fuel pin powers are investigated. The 3-D nodal code, STORM, has been modified to perform these calculations. Several numerical examples lead to the following conclusions: (1) By employing a thermal leakage-to-absorption ratio11 (TLAR) approximation for the spatial shape of the thermal fluxes for the 3-D Langenbuch-Maurer- Werner (LMW) and the superpronipt critical transient problems, the convergence of the conventional two-group scheme is accelerated. The resulting computing time is reduced eight to fourteen times while maintaining computational accuracy. The TLAR acceleration scheme assumes that even if the thermal leakage rate and absorption rate varies significantly in a given node, the ratio of those two changes little during a small time step; (2) By employing the steepest-ascent hill climbing search with heuristic strategies, Optimum Control Rod Pattern Searcher (OCRPS) is developed for solving control rod positioning problem in BWRs. Using the method of approximation programming the objective function and the nuclear and thermal-hydraulic constraints are modified as heuristic functions that guide the search. The test calculations have demonstrated that, for the first cycle of the Edwin Hatch Unit #2 reactor, OCRPS shows excellent performance for finding a series of optimum control rod patterns for six burnup steps during the operating cycle. Computing costs are modest even if the initial guess patterns have extremely deteriorated core characteristics; and (3) For the modified two-dimensional EPRI-9R problem, the least square second-order polynomial flux expansion method was demonstrated to be computationally about 30 times faster than a fine-mesh finite difference calculation in order to achieve comparable accuracy for pin powers. The basic assumption of this method is that the reconstructed flux can be expressed as a product of an assembly form function and a second-order polynomial function. The assembly form function is calculated by solving an assembly criticality calculation. The polynomial function is determined by minimizing the least-squares difference between the intra-nodal quantities obtained from the global two-dimensional coarse-mesh nodal solutions and those obtained from the evaluation of the polynomial function.
Download or read book Reactor Power Transients as Calculated by the Space Independent Reactor Equations written by K. V. Moore and published by . This book was released on 1959 with total page 42 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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 XTRAN a Computer Code for the Calculation of Reactor Transients in Light Water Reactors with Fuel Temperature Feedback written by James Nelson Morgan and published by . This book was released on 1975 with total page 112 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Anticipated and Abnormal Plant Transients in Light Water Reactors written by Pamela Lassahn and published by Springer Science & Business Media. This book was released on 2013-11-11 with total page 725 pages. Available in PDF, EPUB and Kindle. Book excerpt: Over the last 30 years, reactor safety technology has evolved not so much from a need to recover from accidents or incidents, but primarily from many groups in the nuclear community asking hypo thetical, searching (what if) ~uestions. This ~uestioning has indeed paid off in establishing preventive measures for many types of events and potential accidents. Conditions, such as reactivity excursions, large break, loss of coolant, core melt, and contain ment integrity loss, to name a few, were all at one time topics of protracted discussions on hypothesized events. Historically, many of these have become multiyear, large-scale research programs aimed at resolving the "what ifs. " For the topic of anticipated and abnormal plant transients, how ever, the searching ~uestions and the research were not so prolific until the mid-1970s. At that time, probabilistic risk methodolo gies began to tell us we should change our emphasis in reactor safety research and development and focus more on small pipe breaks and plant transients. Three Mile Island punctuated that message in 1979. The plant transient topic area is a multidisciplinary subject involving not only the nuclear, fluid flow, and heat transfer technologies, but also the synergistics of these with the reactor control systems, the safety s;,"stems, operator actions, maintenance and even management and the economic considerations of a given plant.
Download or read book Calculations of Reactivity Behavior During SPERT I Transients written by Richard W. Miller and published by . This book was released on 1957 with total page 38 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Calculation of Power Transients for the SPERT 11 Nuclear Reactor Core with Inclusion of Nucleate Boiling of the Coolant written by A. W. Dalton and published by . This book was released on 1983 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Current Interruption Transients Calculation written by David F. Peelo and published by John Wiley & Sons. This book was released on 2020-04-06 with total page 309 pages. Available in PDF, EPUB and Kindle. Book excerpt: Provides an original, detailed, and practical description of current interruption transients, origins, and the circuits involved, and shows how they can be calculated Based on a course that has been presented by the author worldwide, this book teaches readers all about interruption transients calculation—showing how they can be calculated using only a hand calculator and Excel. It covers all the current interruption cases that occur on a power system and relates oscillatory circuit (transients) and symmetrical component theory to the practical calculation of current interruption transients as applied to circuit breaker application. The book explains all cases first in theory, and then illustrates them with practical examples. Topics featured in Current Interruption Transients Calculation, Second Edition include: RLC Circuits; Pole Factor Calculation; Terminal Faults; Short Line Faults; Inductive Load Switching; and Capacitive Load Switching. The book also features numerous appendices that cover: Differential Equations; Principle of Duality; Useful Formulae; Euler’s Formula; Asymmetrical Current-Calculating Areas Under Curves; Shunt Reactor Switching; and Generator Circuit Breaker TRVs. Offers a clear explanation of how to calculate transients without the use of specialist software, showing how four basic circuits can represent all transients Describes every possible current interruption case that can arise on a power system, explaining them through theory and practical examples Analyses oscillatory circuit (transients) and symmetrical component theory in detail Takes a practical approach to the subject so engineers can use the knowledge in circuit breaker applications Current Interruption Transients Calculation, Second Edition is an ideal book for power electrical engineers, as well as transmission and distribution staff in the areas of planning and system studies, switchgear application, specification and testing, and commissioning and system operation.
Download or read book Reactor Transient written by and published by . This book was released on 1956 with total page 2 pages. Available in PDF, EPUB and Kindle. Book excerpt: The authors are planning a calculation to be done on the Univac at the Louviers Building to estimate the effect of xenon transients, a high reactor power. This memorandum outlines the reasons why they prefer to do the work at Louviers rather than at another location, such as N.Y.U. They are to calculate the response of the reactor to a sudden change in position of the half rods. Qualitatively, the response will be a change in the rooftop ratio of the neutron flux. The rooftop ratio may oscillate with high damping, or, instead, it may oscillate for many cycles. It has not been possible for them to determine this response by hand calculation because of the complexity of the problem, and yet it is important for them to be certain that high power operation will not lead us to inherently unstable operation. Therefore they have resorted to machine computation. The system of differential equations that describes the response has seven dependent variables; therefore there are seven equations, each coupled with one or more of the others. The authors have discussed the problem with R.R. Haefner at the plant, and it is his opinion that the IBM 650 cannot adequately handle the system of seven equations because the characteristic time constants vary over a range of about 108. The Univac located at the Louviers Building is said to be satisfactory for this computation.
Download or read book Investigation of Reactor Transients and Power Patterns of a Heavy Water moderated Boiling Heavy Water cooled Reactor written by C. Graves and published by . This book was released on 1961 with total page 64 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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 TRAC PF1 MOD1 Post Test Calculations of the OECD LOFT Experiment LP SB 1 written by E. J. Allen and published by . This book was released on 1990 with total page 140 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book TRANTEMP written by Bryant N. Kristianson and published by . This book was released on 1968 with total page 112 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Thermal and Reactor Analysis of Nuclear Rocket Transients written by Robert R. Mills and published by . This book was released on 1973 with total page 448 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Measurement and Calculation of Slow Power Transients in the University Training Reactor Moata written by J. W. Connolly and published by . This book was released on 1977 with total page 8 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book PARET written by C. F. Obenchain and published by . This book was released on 1969 with total page 152 pages. Available in PDF, EPUB and Kindle. Book excerpt:
