Published September 1986 | Version v1
Report Metadata-only

PC-based demonstration of BWR reactor vessel level and pressure signal validation

Creators

Description

This paper describes the personal computer (PC)-based demonstration of a computer program to automate the validation of the BWR reactor vessel level and pressure signals. The objective of this demonstration is to show how the signal validation technology can be applied to these specific BWR applications. BWR utility engineers, management, and plant staff are encouraged to use this demonstration to help them better understand the principles and operation of the signal validation methodology. The program may be run on an IBM PC or on any IBM-compatible machines. It is designed to be self-paced and user-friendly

Additional details

Publishing Information

Imprint Title
1985 nuclear power plant safety control technology seminar: proceedings
Journal Page Range
p. C.29-C.43.
Report number
EPRI-NP--4750-SR

Conference

Title
EPRI seminar on nuclear power plant safety control technology.
Dates
4-6 Feb 1985.
Place
Palo Alto, CA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
18041139
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
BWR TYPE REACTORS; COMPUTER CODES; COMPUTERIZED SIMULATION; EDUCATION; MONITORING; ON-LINE CONTROL SYSTEMS; REACTOR CORES; REACTOR OPERATION; REACTOR SAFETY; SIGNALS; VERIFICATION
Descriptors DEC
CONTROL SYSTEMS; ENRICHED URANIUM REACTORS; ON-LINE SYSTEMS; OPERATION; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS