Optimum Boiling Water Reactor Fuel Design Strategies to Enhance Reactor Shutdown by the Standby Liquid Control System

Optimum Boiling Water Reactor Fuel Design Strategies to Enhance Reactor Shutdown by the Standby Liquid Control System
Author: Michael Lorne Fensin
Publisher:
Total Pages:
Release: 2004
Genre: Nuclear reactors
ISBN:

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ABSTRACT: Licensing a commercial nuclear reactor core involves a stringent amount of calculations that demonstrate the capability of safe reactor shutdown in the instance of an emergency transient event. In a boiling water nuclear reactor the control blades and standby liquid control system are the two independent redundant safety systems utilized for shutting down the reactor. In past fuel designs lower power cores with smaller cycle lengths resulting from lower core average enrichment caused shutdown by the control blades to be the most limiting strategy of the two modes for reactor shutdown. This led to a lesser focus on fuel design strategies for standby liquid control system margin (SLCS). Advanced modern core designs involve higher powers and increased cycle lengths resulting from higher core average enrichments, therefore causing SLCS to now become a more significant shutdown parameter.

Aging Assessment of the Boiling-water Reactor (BWR) Standby Liquid Control System

Aging Assessment of the Boiling-water Reactor (BWR) Standby Liquid Control System
Author:
Publisher:
Total Pages: 13
Release: 1992
Genre:
ISBN:

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Pacific Northwest Laboratory conducted a Phase I aging assessment of the standby liquid control (SLC) system used in boiling-water reactors. The study was based on detailed reviews of SLC system component and operating experience information obtained from the Nuclear Plant Reliability Database System, the Nuclear Document System, Licensee Event Reports, and other databases. Sources dealing with sodium pentaborate, borates, boric acid, and the effects of environment and corrosion in the SLC system were reviewed to characterize chemical properties and corrosion characteristics of borated solutions. The leading aging degradation concern to date appears to be setpoint drift in relief valves, which has been discovered during routine surveillance and is thought to be caused by mechanical wear. Degradation was also observed in pump seals and internal valves. In general, however, the results of the Phase I study suggest that age-related degradation of SLC systems has not been serious.

Optimal Shutdown Control of Nuclear Reactors by Milton Ash

Optimal Shutdown Control of Nuclear Reactors by Milton Ash
Author:
Publisher: Elsevier
Total Pages: 186
Release: 1966-01-01
Genre: Mathematics
ISBN: 0080955320

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In this book, we study theoretical and practical aspects of computing methods for mathematical modelling of nonlinear systems. A number of computing techniques are considered, such as methods of operator approximation with any given accuracy; operator interpolation techniques including a non-Lagrange interpolation; methods of system representation subject to constraints associated with concepts of causality, memory and stationarity; methods of system representation with an accuracy that is the best within a given class of models; methods of covariance matrix estimation;methods for low-rank matrix approximations; hybrid methods based on a combination of iterative procedures and best operator approximation; andmethods for information compression and filtering under condition that a filter model should satisfy restrictions associated with causality and different types of memory.As a result, the book represents a blend of new methods in general computational analysis,and specific, but also generic, techniques for study of systems theory ant its particularbranches, such as optimal filtering and information compression. - Best operator approximation,- Non-Lagrange interpolation,- Generic Karhunen-Loeve transform- Generalised low-rank matrix approximation- Optimal data compression- Optimal nonlinear filtering

REPP

REPP
Author: R. M. Hiatt
Publisher:
Total Pages: 196
Release: 1969
Genre: Boiling water reactors
ISBN:

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REPP, a digital computer method for designing pressure water and boiling water reactor cores within specified heat transfer and fuel centerline temperature limits is presented. The method incorporates the Westinghouse W-2 and W-3 empirical correlations and a theoretical hot channel model to predict burnout conditions in a rod bundle. Two geometries are considered; rods in a triangular array and rods in a square lattice. The heat transfer problem solved is a one-dimensional analysis. Pressure drop is considered for four types of fuel-pin spacers. Variable heat generation rate through the fuel-pin and sintering in low density fuels are also included.