Published 1988 | Version v1
Book Metadata-only

Inherent safety and operability testing in RBR-II

Creators

  • 1. Argonne National Lab., Idaho Falls, ID (USA)
  • 2. Argonne National Lab., IL (USA)

Description

This paper discusses how EBR-II is being used to develop advanced safety and operating strategies for next-generation LMR power plants. The work is divided into five categories: control strategy and plant testing; computer simulation; diagnostics; plant automation; and computer reliability. A milestone in the EBR-II program was the conduct of the inherent safety demonstration tests in April 1986. Since then, work has been undertaken on advanced control strategies that are compatible with inherent safety characteristics of metal-fuel LMRs and which also preclude damaging transient overpower events. Six plant tests were conducted in November 1987 to investigate plant maneuverability without control rod action. These tests also provided an opportunity for testing two important diagnostic and display systems. These systems will lay the basis for future automation of EBR-II and follow-on plants

Additional details

Publishing Information

Publisher
American Nuclear Society.
Imprint Place
La Grange Park, IL (USA)
ISBN
89448-1460-0
Imprint Title
Proceedings of the international topical meeting on safety of next generation power reactors
Imprint Pagination
933 p.
Journal Page Range
p. 385-393.

Conference

Title
American Nuclear Society topical meeting on the safety of next generation power reactors.
Dates
1-5 May 1988.
Place
Seattle, WA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
22023245
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTERIZED SIMULATION; EBR-2 REACTOR; ON-LINE CONTROL SYSTEMS; REACTOR OPERATION; REACTOR SAFETY; TESTING
Descriptors DEC
BREEDER REACTORS; CONTROL SYSTEMS; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; ON-LINE SYSTEMS; OPERATION; POWER REACTORS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; SIMULATION; SODIUM COOLED REACTORS

Optional Information

Secondary number(s)
CONF-880506--.