Published 1975 | Version v1
Book

Pressurized water reactor system model for control system design and analysis

  • 1. Westinghouse Nuclear Energy Systems, Pittsburgh

Description

Satisfactory operation of present generation Pressurized Water Reactor (PWR) Nuclear Power systems requires that several independent and interactive control systems be designed. Since it is not practical to use an actual PWR system as a design tool, a mathematical model of the system must be developed as a design and analysis tool. The model presented has been developed to be used as an aid in applying optimal control theory to design and implement new control systems for PWR plants. To be applicable, the model developed must represent the PWR system in its normal operating range. For safety analysis the operating conditions of the system are usually abnormal and, therefore, the system modeling requirements are different from those for control system design and analysis

Additional details

Publishing Information

Publisher
Instrument Society of America.
Imprint Place
Pittsburgh
Imprint Title
Modeling and simulation. Volume 6, Part 1
Imprint Pagination
p. 89-93.

Conference

Title
6. annual conference on modeling and simulation.
Dates
24 Apr 1975.
Place
Pittsburgh, Pennsylvania, USA.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
7275794
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
MATHEMATICAL MODELS; PWR TYPE REACTORS; REACTOR CONTROL SYSTEMS; SPECIFICATIONS
Descriptors DEC
CONTROL SYSTEMS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
Imprint:See CONF-750418--P1.