Published April 1983 | Version v1
Report

Scaling considerations for FLECHT-SEASET

Description

The NRC/EPRI/W FLECHT-SEASET systems effects test facility was originally designed to study low pressure reflood PWR systems behavior. The facility was modified to also study single-phase, two-phase, and reflux condensation natural circulation transients which are more typical of a high pressure PWR small break LOCA or operational transient. The question of how to design the scaled facility to study each of these diverse conditions had to be addressed. The traditional scaling approaches such as linear, power to volume, volumetric, and dimensionless numbers, were examined and evaluated for each test before power to volume was selected. The thermal-hydraulic phenomena for each type of test was reviewed and the primary driving forces for each test identified and preserved. Since the pressure which was to be simulated in the two experiments was significantly different, two-phase flow scaling approaches were examined, particularly for the reflux condensation natural circulation tests. The paper will describe the scaling basis chosen for each test series and will highlight where the scaling compromises were and how they were technically resolved

Additional details

Publishing Information

Imprint Title
Joint NRC/ANS meeting on basic thermal-hydraulic mechanisms in LWR analysis
Journal Page Range
p. 235-251.
Report number
NUREG/CP--0043

Conference

Title
NRC/ANS meeting on basic thermal hydraulic mechanisms in LWR analysis.
Dates
14-15 Sep 1982.
Place
Bethesda, MD (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
15010207
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CORE FLOODING SYSTEMS; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; PWR TYPE REACTORS; REACTOR SAFETY; SCALE MODELS; SCALING LAWS; TESTING
Descriptors DEC
ACCIDENTS; ECCS; ENERGY TRANSFER; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; STRUCTURAL MODELS; WATER COOLED REACTORS; WATER MODERATED REACTORS