PDF/Textbook In Core Fuel Management For Pressurized Water Reactors Full Download

In-core Fuel Management for Pressurized Water Reactors

Author: Frederic Kolenda
Publisher:
ISBN:
Category :
Languages : en
Pages : 374

Book Description

Optimal In-Core Fuel Management for the Pressurized Water Reactor

Author: Shafiq Y. Hurani
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 198

Book Description

Optimization of In-core Nuclear Fuel Management in a Pressurized Water Reactor

Author: Richard Bartholomew Stout
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 316

Book Description
Fuel loading patterns which have a minimum power peak are economically desirable to allow power reactors to operate at the highest possible power density and to minimize the possibility of fuel failure. A computer code called SHUFLE was developed for pressurized water reactors which shuffles the fuel in search of the lowest possible power peaking factor. An iterative approach is used in this search routine. A radial power distribution is calculated from which the program logic Selects a movement of fuel elements in an attempt to lower the radial power peak. Another power calculation is made and the process repeated until a predetermined convergence is reached. The logic by which the code decides the fuel movement is presented, along with the criteria for accepting or rejecting the move after a power calculation of the new loading pattern is made. A 1.5 group course mesh diffusion theory method was used to obtain the power distribution for each SHUFLE iteration. Convergence to a final loading pattern varies from about 10 to 40 shuffling iterations depending on the initial loading presented to the code. Since the typical computer running time for a one-quarter core power distribution with this 1.5 group method is only one to a few seconds, depending on the loading, convergence to a good loading pattern takes on the order of one minute on a Univac 1108. The low computer cost plus ease of operation should make this code of considerable use in determining loading patterns with minimum power peaking for any given set of fuel elements. The program also has burnup capability which can be used to check power peaking throughout core life. A parametric analysis study of fuel cycle costs for a PWR is also presented. Cost parameters analyzed were variation in the cost of yellow cake, enrichment, money, fabrication, and reprocessing plus changes in burnup, load factors, power densities, and the effect of forced early discharge. Figures are presented to indicate total fuel costs as a function of burnup for these cost parameters. Linear relationships for minimum cost and optimum burnup are presented for each parameter.

Fuel Management in Large Pressurized Water Reactors

Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description
Economic and operational ground rules and their effects on fuel management are summarized, and examples showing the approach to typical fuel management problems are presented. The problems associated with in-core fuel management are also discussed, and the merits of various fuel cycling methods are evaluated. (D.C.W.).

Design of the Reactor Core for Nuclear Power Plants

Author: IAEA
Publisher: International Atomic Energy Agency
ISBN: 9201076223
Category : Technology & Engineering
Languages : en
Pages : 87

Book Description
The reactor core is the central part of a nuclear reactor where nuclear fission occurs. It consists of four basic systems and components: the fuel (including fuel rods and the fuel assembly structure), the coolant, the moderator and the control rods, as well as additional structures such as reactor pressure vessel internals, core support plates, and the lower and upper internal structure in light water reactors. This Safety Guide provides recommendations on meeting the safety requirements established in IAEA Safety Standards Series No. SSR-2/1 (Rev. 1), Safety of Nuclear Power Plants: Design, applied to the design of the reactor core for nuclear power plants. The publication addresses the safety aspects of the core design and includes neutronic, thermohydraulic, thermomechanical and structural mechanical aspects. Other aspects considered are those relating to reactor core control, shutdown and monitoring, and core management.

Non-Proliferative, Thorium-Based, Core and Fuel Cycle for Pressurized Water Reactors

Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description
Two of the major barriers to the expansion of worldwide adoption of nuclear power are related to proliferation potential of the nuclear fuel cycle and issues associated with the final disposal of spent fuel. The Radkowsky Thorium Fuel (RTF) concept proposed by Professor A. Radkowsky offers a partial solution to these problems. The main idea of the concept is the utilization of the seed-blanket unit (SBU) fuel assembly geometry which is a direct replacement for a 'conventional' assembly in either a Russian pressurized water reactor (VVER-1000) or a Western pressurized water reactor (PWR). The seed-blanket fuel assembly consists of a fissile (U) zone, known as seed, and a fertile (Th) zone known as blanket. The separation of fissile and fertile allows separate fuel management schemes for the thorium part of the fuel (a subcritical 'blanket') and the 'driving' part of the core (a supercritical 'seed'). The design objective for the blanket is an efficient generation and in-situ fissioning of the U233 isotope, while the design objective for the seed is to supply neutrons to the blanket in a most economic way, i.e. with minimal investment of natural uranium. The introduction of thorium as a fertile component in the nuclear fuel cycle significantly reduces the quantity of plutonium production and modifies its isotopic composition, reducing the overall proliferation potential of the fuel cycle. Thorium based spent fuel also contains fewer higher actinides, hence reducing the long-term radioactivity of the spent fuel. The analyses show that the RTF core can satisfy the requirements of fuel cycle length, and the safety margins of conventional pressurized water reactors. The coefficients of reactivity are comparable to currently operating VVER's/PWR's. The major feature of the RTF cycle is related to the total amount of spent fuel discharged for each cycle from the reactor core. The fuel management scheme adopted for RTF core designs allows a significant decrease in the amount of discharged spent fuel, for a given energy production, compared with standard VVER/PWR. The total Pu production rate of RTF cycles is only 30 % of standard reactor. In addition, the isotopic compositions of the RTF's and standard reactor grade Pu are markedly different due to the very high burnup accumulated by the RTF spent fuel.

In-core Fuel Management for Pressurized Water Reactors

Optimal In-Core Fuel Management for the Pressurized Water Reactor

Optimization of In-core Nuclear Fuel Management in a Pressurized Water Reactor

Fuel Management in Large Pressurized Water Reactors

Design of the Reactor Core for Nuclear Power Plants

Non-Proliferative, Thorium-Based, Core and Fuel Cycle for Pressurized Water Reactors

Nuclear Reactor Core Fuel Cycle Analysis and Computation for Pressurized Water Reactors

Nuclear Fuel Management

The Pennsylvania State University Pressurized Water Reactor Fuel Management Package User's Guide

Fuel Management Strategies for Pressurized Water Reactors