Published 1997 | Version v1
Journal article

Evaluation of low flow characteristics of the Vermont Yankee plant

  • 1. Yankee Atomic Electric Co., Bolton, MA (United States)

Description

Boiling water reactor (BWR) core flow instrumentation inaccuracies under low-flow conditions have been the subject of both reactor vendor and regulatory communications in response to incidents of the reported core flow being less than the flow corresponding to the natural-circulation line on the power flow map. During single recirculation loop operation, low-flow conditions exist in the idle recirculation loop, and these flow inaccuracies can affect the usefulness of the reported core flow. Accurate core flow indications are needed above 25% power to administer fuel thermal limits and comply with restrictions associated with the potential for thermal-hydraulic instability. While the natural-circulation line on the power flow map is recognized to be a nominal estimate of the flow expected at and near natural-circulation conditions, the boundaries of the stability regions are associated with conditions assumed in safety analyses performed to demonstrate compliance with general design criteria 10 and 12

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
77
Journal Page Range
p. 439-440.
ISSN
0003-018X
CODEN
TANSAO

Conference

Title
1997 American Nuclear Society (ANS) winter meeting.
Dates
16-20 Nov 1997.
Place
Albuquerque, NM (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
29021149
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
F CODES; HYDRAULICS; REACTOR COOLING SYSTEMS; REACTOR SAFETY; VERMONT YANKEE REACTOR
Descriptors DEC
BWR TYPE REACTORS; COMPUTER CODES; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
CONF-971125--.