2 edition of Optimization of in-core nuclear fuel management in a pressurized water reactor found in the catalog.
Optimization of in-core nuclear fuel management in a pressurized water reactor
Richard Bartholomew Stout
Written in English
|Statement||by Richard Bartholomew Stout.|
|The Physical Object|
|Pagination||, 158 leaves, bound :|
|Number of Pages||158|
The liquid fluoride thorium reactor (LFTR; often pronounced lifter) is a type of molten salt use the thorium fuel cycle with a fluoride-based, molten, liquid salt for a typical design, the liquid is pumped between a critical core and an external heat exchanger where the heat is transferred to a nonradioactive secondary salt. The secondary salt then transfers its . One of the most important problems in the in core fuel management optimization is to select a proper objective function. In a nuclear reactor, there are so many parameters which can be selected as cost function. Among In this investigation, we analyzed these effects on the fuel management optimization of a typical pressurized water.
Workings of a Nuclear Reactor. Reactor Basics PWR BWR Key Reactor Power Terms Availability Fraction of time over a reporting period that the plant is operational If a reactor is down for maintenance 1 week and refueling 2 weeks every year, the availability factor of the reactor would be (( * 7) / = Key Reactor Power Terms. Chinese integrated pressurized water reactor (CIPWR) has compact configuration and high inherent safety, which is appropriate for nuclear power plants of small and medium scale. Heat balance model has been adopted widely in thermal power calibration of PWRs because of its advantage of accuracy. In this paper, a package based on FORTRAN language is developed Author: Zhang Fan, Lu Dao-Gang, Sui Dan-Ting, Guo Chao, Yuan Bo.
The nuclear fuel cycle, also called nuclear fuel chain, is the progression of nuclear fuel through a series of differing stages. It consists of steps in the front end, which are the preparation of the fuel, steps in the service period in which the fuel is used during reactor operation, and steps in the back end, which are necessary to safely manage, contain, and either reprocess or dispose of Author: David J Strumfels. standards and measures are issued in the IAEA Safety Standards Series. This series covers nuclear safety, radiation safety, transport safety and waste safety, and also general safety (that is, of relevance in two or more of the four areas), and the categories within it are Safety Fundamentals, Safety Requirementsand Safety Guides.
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Abstract. This paper reports on an in-core nuclear fuel management code for pressurized water reactor reload design developed that combines the stochastic optimization technique of simulated annealing with a computationally efficient core physics model based on second-order accurate generalized perturbation theory.
Introduction. The design of pressurized water reactors (PWR) reload cores is a formidable combinatorial optimization problem. The designer’s task is to find the configuration of fresh and partially burnt fuel and burnable poisons (BPs) that optimizes the performance of the reactor over the subsequent cycle, while ensuring that various operational constraints are by: Buy HEURISTIC RULES IN GENETIC ALGORITHM FOR FUEL MANAGEMENT OPTIMIZATION: In-Core Fuel Management Optimization for Pressurized Water Reactors (PWRs) on FREE SHIPPING on qualified orders5/5(1).
Also known as In-Core Fuel Management Optimization, the LP optimization is a prominent real-world problem in Nuclear Engineering with high complexity due to its combinatorial formulation with a large number of feasible solutions, a large number of sub-optimal solutions, disconnected feasible regions, high dimensionality, complex and time Author: Anderson Alvarenga de Moura Meneses, Lenilson Moreira Araujo, Fernando Nogueira Nast, Patrick Vascon.
An in-core nuclear fuel management code for pressurized water reactor reload design has been developed that combines the stochastic optimization technique of simulated annealing with a.
D.J. Kropaczek and P.J. Turinsky, In-core nuclear fuel management optimization for pressurized water reactors utilizing simulated annealing, Nuclear Technology ().
Google Scholar Cited by: A. YamamutoComparison between equilibrium cycle and successive multicycle optimization methods for in-core fuel management of pressurized water reactors Proceedings of Joint International Conference on Math, Methods and Supercomp, for Nuclear Application, American Nuclear Society Inc, Saratoga Springs, New York (), pp.
Cited by: This article describes the light water reactor optimizer (LWROpt), a fuel cycle optimization code originally developed for BWRs, which has been adapted to perform core fuel reload and/or operational control rod management for pressurized water reactors (PWRs) and small modular reactors (SMRs), as by: 1.
The nuclear fuel cycle, also called nuclear fuel chain, is the progression of nuclear fuel through a series of differing stages. It consists of steps in the front end, which are the preparation of the fuel, steps in the service period in which the fuel is used during reactor operation, and steps in the back end, which are necessary to safely manage, contain, and either reprocess or dispose of.
Optimization of the arrangement of fuel assemblies and burnable poisons when reloading pressurized water reactors has, in the past, been performed with many di erent algorithms in an attempt to make reactors more economic and fuel effi cient. A nuclear reactor core is the portion of a nuclear reactor containing the nuclear fuel components where the nuclear reactions take place and the heat is generated.
Typically, the fuel will be low-enriched uranium contained in thousands of individual fuel pins. The core also contains structural components, the means to both moderate the neutrons and control the reaction, and the. An Overview of AI Methods for in-Core Fuel Management: Tools for the Automatic Design of Nuclear Reactor Core Conﬁgurations for Fuel Reload, (Re)arranging New and Partly Spent Fuel Ephraim Nissan 1 London, UK; @ 2 Formerly of the Department of Computing, Goldsmiths College of the University of London, New Cross,Author: Ephraim Nissan.
A conceptual design of China supercritical water-cooled reactor with the rated electric power of MW e (CSR) core was proposed with features such as single water rod, combined square fuel assembly (FA) with stainless steel fuel cladding and structure material, two flow-pass of coolant in core, high-leakage reload core with FAs Cited by: 2.
OPTIMIZATION OF IN-CORE IN,CA'NDU NUCL~A.R I I I. FUEL MANAGEMENT REACTORS. • (0 DANIEL ROZON, B.A., A., '• ' A Thesis Submitted to the School of Graduate Studies in Partial Fulfilment of the RequirementsAuthor: Daniel Rozon.
The invention is applicable to the field of fuel management on reactor cores of pressurized water reactors, and provides a refueling method for fuel assemblies of a reactor core of a PWR (pressurized water reactor) nuclear power plant.
The method comprises: classifying the fuel assemblies of the reactor core into three enrichment areas according to different enrichment Author: 肖岷, 高立刚, 张洪, 李雷, 韩庆浩, 戴忠华, 李晓明.
include water and fast reactor safety, siting, and neutron physics. AN EQUILIBRIUM APPROACH TO OPTIMAL IN-CORE J. Dias D. Okrent R. Erdmann FUEL MANAGEMENT FOR PRESSURIZED WATER RE- Krishan Chitkara ACTORS Joel Weisman Krishan Chitkara (left) (PhD, nuclear engineering, Univer.
An important aspect of managing a nuclear reactor is how to design refuellings, and from the s to the present different artificial intelligence (AI) techniques have been applied to this problem.
A section of the reactor core resembles a symmetrical grid; long fuel assemblies are inserted there, some of them new, some of them partly spent.
Rods of “burnable Author: Ephraim Nissan. In the multiobjective in-core fuel management optimization (MICFMO) problem, the aim is to identify a Pareto optimal set of compromise or trade-off reload configurations.
Such a set may then be presented to a decision maker (i.e. a nuclear reactor operator) for consideration so as to select a preferred by: 2.
Nuclear Reactor Engineering: Reactor Systems Engineering Samuel Glasstone, Alexander Sesonske (auth.) Dr. Samuel Glasstone, the senior author of the previous editions of this book, was anxious to live until his ninetieth birthday, but passed away in.
The Reactor Physics Analysis Group functions in two major domains: 1) technical support of MITR operation and experiment and 2) cutting edge investigation of advanced reactor concepts and innovative test reactor design.
The code system used in the group and on-going research projects are presented below. Workings of a Nuclear Reactor. Reactor Basics PWR BWR Key Reactor Power Terms Availability Fraction of time over a reporting period that the plant is operational If a reactor is down for maintenance 1 week and refueling 2 weeks every year, the availability factor of the reactor would be ( * 7) / = Key Reactor Power Terms Capacity Fraction of total electric power.
The nuclear fuel cycles describes how nuclear fuel is extracted, processed, used, and disposed of. The nuclear fuel cycle, also called nuclear fuel chain, is the progression of nuclear fuel through a series of differing stages.
It consists of steps in the front end, which are the preparation of the fuel, steps in the service period in which the fuel is used during reactor. In the design method for nuclear reactor fuel management, nuclear reactor operation for sets of independent control variable values is simulated to produce associated sets of dependent performance var.