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An Improved Method For Calculating Control Rod Reactivity Worths In Fast Sodium Cooled Reactor Cores
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Book Synopsis An improved method for calculating control rod reactivity worths in fast sodium cooled reactor cores by :
Download or read book An improved method for calculating control rod reactivity worths in fast sodium cooled reactor cores written by and published by . This book was released on 1993 with total page 60 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis An Improved Method for Calculating Control Rod Reactivity Worths in Fast Sodium Cooled Reactor Cores by : W. Zwermann
Download or read book An Improved Method for Calculating Control Rod Reactivity Worths in Fast Sodium Cooled Reactor Cores written by W. Zwermann and published by . This book was released on 1993 with total page 60 pages. Available in PDF, EPUB and Kindle. Book excerpt: "An improved method is presented to determine the reactivities of strongly inhomogeneous control rod arrangements in fast sodium cooled reactor cores. The method is based on a detailed evaluation of the multiplication constants for the rods embedded in a large surrounding of fuel material"--Abstract.
Book Synopsis Reactivity Worth of Sodium in Sodium Cooled Reactors by : R. W. Keaten
Download or read book Reactivity Worth of Sodium in Sodium Cooled Reactors written by R. W. Keaten and published by . This book was released on 1961 with total page 32 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis An Improved Method for Calculating Control Rod Reactivity Worths in Fast Sodium Cooled Reactor Cores by : Winfried Zwernemann
Download or read book An Improved Method for Calculating Control Rod Reactivity Worths in Fast Sodium Cooled Reactor Cores written by Winfried Zwernemann and published by . This book was released on 2018 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis An Improved Method for Calculating Control Rod Reactivity Worths in Fast Sodium Colled Reactor Cores by : W. Zwermann
Download or read book An Improved Method for Calculating Control Rod Reactivity Worths in Fast Sodium Colled Reactor Cores written by W. Zwermann and published by . This book was released on 1993 with total page 60 pages. Available in PDF, EPUB and Kindle. Book excerpt: "An improved method is presented to determine the reactivities of strongly inhomogeneous control rod arrangements in fast sodium cooled reactor cores. The method is based on a detailed evaluation of the multiplication constants for the rods embedded in a large surrounding of fuel material"--Abstract.
Book Synopsis Reactivity Worths of Several Fast Reactor Control Materials by : R. W. Campbell
Download or read book Reactivity Worths of Several Fast Reactor Control Materials written by R. W. Campbell and published by . This book was released on 1965 with total page 42 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis American National Standard Calculation and Measurement of the Modular Temperature Coefficient of Reactivity for Water Moderated Power Reactors by : American National Standards Institute
Download or read book American National Standard Calculation and Measurement of the Modular Temperature Coefficient of Reactivity for Water Moderated Power Reactors written by American National Standards Institute and published by . This book was released on 1997 with total page 32 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis A Direct Method for the Measurement of Control Rod Worth in a Nuclear Reactor by : William Arthur Emslie
Download or read book A Direct Method for the Measurement of Control Rod Worth in a Nuclear Reactor written by William Arthur Emslie and published by . This book was released on 1972 with total page 152 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis An Approximate Method for Calculating Control Rod Positions in a Fast Reactor by : Michael Robert Figueira
Download or read book An Approximate Method for Calculating Control Rod Positions in a Fast Reactor written by Michael Robert Figueira and published by . This book was released on 1975 with total page 316 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Benchmark Analyses on the Control Rod Withdrawal Tests Performed During the Phenix End-Of-Life Experiments by :
Download or read book Benchmark Analyses on the Control Rod Withdrawal Tests Performed During the Phenix End-Of-Life Experiments written by and published by International Atomic Energy Agency. This book was released on 2014-09-18 with total page 247 pages. Available in PDF, EPUB and Kindle. Book excerpt: The benchmark analyses were carried out comparing the results of the calculation with the large amount of experimental data obtained in Phenix. Moreover, the evaluation of a large set of plant parameters allowed performing accurate code-to-code comparisons, with the overall purpose to understand the critical open issues and recognize gaps which will require further investigations.
Book Synopsis Analysis of Advanced Sodium-cooled Fast Reactor Core Designs with Improved Safety Characteristics by : Kaichao Sun
Download or read book Analysis of Advanced Sodium-cooled Fast Reactor Core Designs with Improved Safety Characteristics written by Kaichao Sun and published by . This book was released on 2012 with total page 180 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Effect of Core Size on Rod Worth During a Control Rod Drop Accident by : Kelly Mcclure
Download or read book Effect of Core Size on Rod Worth During a Control Rod Drop Accident written by Kelly Mcclure and published by . This book was released on 2015 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A control rod drop accident (CRDA) is a reactivity-initiated transient event analyzed by engineers for boiling water reactors (BWRs). During a CRDA, a control rod drops from the core at a high speed, causing a reactivity spike and risking damage to the fuel and cladding. Engineers must prove that a reactor's core design will remain safe in the event of such an accident. Thus, to gain a full understanding of the effect and severity of a CRDA, it is beneficial to explore the effect of reactor core size on the transient results.Beginning with the largest available BWR reactor core, five common BWR core sizes were created and a CRDA was simulated at each size. The initial core re-sizing methodology was developed at GE Hitachi Nuclear Energy, then the process was repeated and the CRDA simulation was performed at Penn State. The goal of the core reduction process was to create core that could be considered "similar" for the CRDA analysis, as defined by adherence to a ±0.005 eigenvalue limit between the calculated and expected leakage-adjusted values.A CRDA was simulated in the five core sizes to compare the severity of the transient event -- as defined by the rod worth of a particular rod of interest. The accident simulation indicated that the rod worth, and thus fuel enthalpy increase, decreases as the core size increases. The same trend was found when comparing power peaking factor (FQ) in the various core sizes. These results suggest that smaller cores yield a more limiting control rod drop accident.
Book Synopsis Monte Carlo Calculations of Control-rod Worth of a Medium-size Pebble-bed Reactor by :
Download or read book Monte Carlo Calculations of Control-rod Worth of a Medium-size Pebble-bed Reactor written by and published by . This book was released on 1982 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Three-dimensional full-core control-rod worth calculations by the Monte Carlo method are performed for a 1640 MW(t) pebble-bed reactor. The worths of all control rods at several insertions are investigated. The reactivity provided by the control rods in the 1-meter void above the core is about 3% and a 20% negative reactivity can be obtained by axially inserting all control rods 3/4 into the reactor core. The multigroup KENO Monte Carlo code with a six-group neutron cross-section library was used in the calculations.
Download or read book Energy Research Abstracts written by and published by . This book was released on 1994-05 with total page 438 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 KfK written by and published by . This book was released on 1993 with total page 70 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Improving Fuel Cycle Design and Safety Characteristics of a Gas Cooled Fast Reactor by : Willem Frederik Geert van Rooijen
Download or read book Improving Fuel Cycle Design and Safety Characteristics of a Gas Cooled Fast Reactor written by Willem Frederik Geert van Rooijen and published by IOS Press. This book was released on 2006 with total page 160 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Generation IV Forum is an international nuclear energy research initiative aimed at developing the fourth generation of nuclear reactors, envisaged to enter service halfway the 21st century. One of the Generation IV reactor systems is the Gas Cooled Fast Reactor (GCFR), the subject of study in this thesis. The Generation IV reactor concepts should improve all aspects of nuclear power generation. Within Generation IV, the GCFR concept specifically targets sustainability of nuclear power generation. The Gas Cooled Fast Reactor core power density is high in comparison to other gas cooled reactor concepts. Like all nuclear reactors, the GCFR produces decay heat after shut down, which has to be transported out of the reactor under all circumstances. The layout of the primary system therefore focuses on using natural convection Decay Heat Removal (DHR) where possible, with a large coolant fraction in the core to reduce friction losses.
