Download or read book Reactor Physics Design of Supercritical CO2 cooled Fast Reactors written by Michael Alexander Pope and published by . This book was released on 2004 with total page 140 pages. Available in PDF, EPUB and Kindle. Book excerpt: (Cont.) Overall, present work confirmed that the S-CO2-cooled GFR concept has promising characteristics and a sufficiently broad opion space such that a safe and competitive design could be developed in future work with considerably less than $1 void reactivity and a controllable [delta]k due to burnup.
Download or read book Optimized Core Design of a Supercritical Carbon Dioxide cooled Fast Reactor written by Christopher Stanley Handwerk and published by . This book was released on 2007 with total page 367 pages. Available in PDF, EPUB and Kindle. Book excerpt: (Cont.) Alternative cores using traditional pin-type fuel and innovative Internally-Cooled Annular Fuel (ICAF) have also been evaluated. While the performance of the TID core is superior, the results of the pin-type core show promise, pending design modification and relaxation of the imposed core pressure drop constraint, which would come at the expense of cycle efficiency and increased decay heat removal power requirements. Nevertheless, no improvement would be able to achieve a sustainable core (i.e. conversion ratio=l) using oxide fuel without the use of external blankets for pin fuel, even without the use of diluent in the fuel. A comprehensive comparison of the thermal hydraulic and neutronic performance of TID fuel with that of the traditional pin-type fuel, as well as with the ICAF is also made, showing the fundamental reasons for their difference in performance.
Download or read book Thermal Hydraulic Design of a 2400 MW T h Direct Supercritical CO2 cooled Fast Reactor written by Michael Alexander Pope and published by . This book was released on 2006 with total page 244 pages. Available in PDF, EPUB and Kindle. Book excerpt: (cont.) The loss of external load (LOEL) event is analyzed and a bypass valve scheme is recommended which prevents shaft overspeed and excessive core coolant mass flow rate. A large dry pressurized water reactor (PWR) containment building having a free volume of 70,000 m3 and a peak design pressure of 6 bar is selected for this design based on a 100 in2 cold duct break. During this same loss of coolant accident (LOCA), the depressurization time is shown to be in excess of 10 minutes. No action need be taken by the SCS/ECS blowers before this time in order to prevent core damage. After this time, a total blower power less than 90 kW is sufficient to cool the core out to 10,000 seconds. A loss of flow (LOF) transient in which a PCS loop is instantaneously isolated and no mitigating action is taken (i.e. no reactor scram) is also shown not to cause core damage. It is concluded that a large S-CO2 cooled GFR coupled to a supercritical Brayton power conversion system can withstand the thermal hydraulic challenges posed by the usual menu of severe accident scenarios.
Download or read book Reactor Physics Methods and Applications written by Tengfei Zhang and published by Frontiers Media SA. This book was released on 2022-06-29 with total page 272 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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.
Download or read book An Evaluation of Gas cooled Fast Reactor written by Oak Ridge National Laboratory and published by . This book was released on 1969 with total page 260 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Core Design and Reactor Physics of a Breed and Burn Gas cooled Fast Reactor written by Peter Yarsky and published by . This book was released on 2005 with total page 248 pages. Available in PDF, EPUB and Kindle. Book excerpt: (Cont.) The B & B GFR designs, though requiring active decay heat removal, are semi-self-regulating from a reactivity feedback standpoint and are designed to withstand all plausible accident scenarios, including loss of flow, loss of heat sink, and transient overpower all without scram. Reactor pressure vessel blowdown (LOCA) was investigated and while the B & B GFR has a low positive coolant void reactivity (less than 1$), the added reactivity during blowdown is compensated through other strong negative reactivity feedback mechanisms, thereby allowing for the safe operation of the B & B GFR.
Download or read book Handbook of Generation IV Nuclear Reactors written by Igor Pioro and published by Woodhead Publishing. This book was released on 2022-12-07 with total page 1112 pages. Available in PDF, EPUB and Kindle. Book excerpt: Handbook of Generation IV Nuclear Reactors, Second Edition is a fully revised and updated comprehensive resource on the latest research and advances in generation IV nuclear reactor concepts. Editor Igor Pioro and his team of expert contributors have updated every chapter to reflect advances in the field since the first edition published in 2016. The book teaches the reader about available technologies, future prospects and the feasibility of each concept presented, equipping them users with a strong skillset which they can apply to their own work and research. Provides a fully updated, revised and comprehensive handbook dedicated entirely to generation IV nuclear reactors Includes new trends and developments since the first publication, as well as brand new case studies and appendices Covers the latest research, developments and design information surrounding generation IV nuclear reactors
Download or read book Implementation of Vented Fuel Assemblies in the Supercritical CO2 cooled Fast Reactor written by Stephanie A. McKee and published by . This book was released on 2008 with total page 159 pages. Available in PDF, EPUB and Kindle. Book excerpt: (Cont.) The radioactive volatiles which remain in the primary comprise only tritium, two isotopes of iodine, two isotopes of tellurium, and three isotopes of cesium. These species deposit on primary surfaces to a great enough degree to preclude hands-on primary system maintenance. In addition, techniques for removal of volatile and radioactive species from the primary coolant were identified, and a scheme for purification of the primary coolant volume was selected. The analysis confirms that primary coolant activity can be maintained at acceptable levels when purification of the primary coolant volume occurs once per hour. The response of the vent system to changes in primary system pressure was also investigated. In particular, the small periodic pressure transients known as breathing were studied, as were loss-of-coolant type scenarios. Both cases were investigated using hand calculations and computational techniques, and the radiological consequences of each were addressed. The analysis demonstrated the ability of the vented fuel assembly to quickly equalize pressure in the event of a sudden drop in operating pressure, and also showed the ability of a succession of plena to prevent the expulsion of much of the activity inventory of the plena during a breathing transient. Conversely, the use of a single plenum results in reduced activity release during a LOCA. After consideration of both results, a two-plenum approach, with a large lower annular plenum following a small upper axial plenum, was selected as the final design.
Download or read book Development of Thermodynamic Cycles for Sodium cooled fast Reactors written by Alexey Dragunov and published by . This book was released on 2013 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Liquid Metal Cooled Reactors written by International Atomic Energy Agency and published by . This book was released on 2007 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: Presents a survey of worldwide experience gained with fast breeder reactor design, development and operation. Coverage includes state of the art of liquid metal fast reactor development; lead-bismuth cooled (LBC) ship reactor operation experience and LBC fast power reactor development; and treatment and disposal of spent sodium.
Download or read book Power Conversion System Design for Supercritical Carbon Dioxide Cooled Indirect Cycle Nuclear Reactors written by Jonathan Paul Gibbs and published by . This book was released on 2008 with total page 207 pages. Available in PDF, EPUB and Kindle. Book excerpt: (Cont.) Peak cycle pressure is also an important parameter affecting cycle efficiency, although to a smaller extent than turbine inlet temperature. Higher pressure gives higher efficiency, but this gradually saturates around 28 MPa. Other sensitivity studies included turbomachinery performance, cooling water temperature, and heat exchanger fouling and plugging The reference parameters chosen are a 650°C turbine inlet temperature and 20 MPa peak cycle pressure (compressor outlet) because they reach a high thermodynamic efficiency (~/~47-48%) while staying within materials limitations. In order to couple the cycle to many of the Generation IV nuclear reactors a second reference case was chosen with a turbine inlet temperature of 550°C and a peak cycle pressure of 20 MPa.
Download or read book An Evaluation of the Gas Cooled Fast Reactor written by U.S. Atomic Energy Commission. Division of Reactor Development and Technology and published by . This book was released on 1972 with total page 56 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Evaluation of Coolants and Moderators for the Maritime Gas cooled Reactor written by and published by . This book was released on 1958 with total page 478 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Fast Oxide Breeder Reactor Physics written by P. Greebler and published by . This book was released on 1959 with total page 66 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book PHYSICS DESIGN OF THE GAS COOLED FAST BREEDER REACTOR DEMONSTRATION PLANT 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 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.
