Published 1987 | Version v1
Journal article

Stability tests in the Grand Gulf unit 1 boiling water reactor

  • 1. Oak Ridge National Lab., TN (USA)

Description

This paper summarizes the results of a series of tests performed on January 31, 1987, to determine the stability of the second reload core in the Grand Gulf Unit 1 boiling water reactor (BWR). The subject of BWR stability is relevant for commercial BWR operation. Utilities are required to evaluate reactor stability for every reload core unless plant technical specifications provide for monitoring of neutron flux oscillations in the so-called limit-cycle detect and suppress region at low flows. The parameter of merit for stability calculations or measurements is the asymptotic decay ratio (DR). The definition of asymptotic DR guarantees that as long as its value is < 1.0, the reactor is stable. The DR also yields a quantitative measure of relative stability: DRs below 0.5 are considered very stable. A noise analysis technique was implemented in a portable computer system, which uses standard commercially available hardware, and was used to perform stability measurements on line. This technique has proven to be fairly accurate for high DRs, when the reactor is close to the stability threshold. For low DR conditions, however, the technique yields only reasonable accuracy. An attempt to quantify this accuracy has been made, and the resulting error bands are presented

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
55
Series
Trans. Am. Nucl. Soc.
Journal Page Range
603-604
ISSN
0003-018X
CODEN
TANSA

Conference

Title
American Nuclear Society winter meeting.
Dates
15-19 Nov 1987.
Place
Los Angeles, CA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
20003726
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ACCURACY; GRAND GULF-1 REACTOR; NEUTRON FLUX; REACTOR FUELING; REACTOR NOISE; REACTOR PHYSICS; REACTOR STABILITY; SPECIFICATIONS; TESTING
Descriptors DEC
BWR TYPE REACTORS; ENRICHED URANIUM REACTORS; POWER REACTORS; RADIATION FLUX; REACTORS; STABILITY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
CONF-8711195--.