Published March 2017 | Version v1
Journal article

Critical heat flux tests for a 12 finned-element assembly

Description

Highlights: • CHF tests for a 12 finned-fuel-element assembly at highly subcooled conditions. • Test approach to maximize experimental information and minimize heater failures. • Three series of tests were completed in vertical upward light water flow. • Bundle simulators of two axial power profiles and three heated lengths were tested. • Results confirm that the prediction method predicts lower CHF values than measured. - Abstract: An experimental study was undertaken to provide relevant data to validate the current critical heat flux (CHF) prediction method of the NRU driver fuel for safety analysis, i.e., to confirm no CHF occurrence below the predicted values. The NRU driver fuel assembly consists of twelve finned fuel elements arranged in two rings – three in the inner ring and nine in the outer ring. To satisfy the experimental objective tests at very high heat fluxes, very high mass velocities, and high subcoolings were conducted where the CHF mechanism is the departure from nucleate boiling (DNB). Such a CHF experiment can be very difficult, costly and time consuming since failure of the heating surface due to rupture or melting (physical burnout) is expected when the DNB type of CHF is reached. A novel experimental approach has been developed to maximize the amount of relevant experimental information on safe operating conditions in the tests, and to minimize any possible heater failures that inherently accompany the CHF occurrence at these conditions. Three series of tests using electrically heated NRU driver fuel simulators with three heated lengths and two axial power profiles (or axial heat flux distribution (AFD)) were completed in vertical upward light water flow. Each series of tests covered two mass flow rates, several heat flux levels, and local subcoolings that bound the ranges of interest for the analysis of postulated slow loss-of-regulation accident (LORA) and loss-of-flow accident (LOFA) scenarios. Tests for each mass flow rate of each test series were performed following a specific heat flux vs. local subcooling test trajectory, which was designed to allow for measurements at sufficiently wide local conditions. The experimental results confirmed that the current CHF prediction method predicts lower CHF values than experimentally measured using the NRU driver fuel rod simulators. This paper introduces the experimental approach, describes the experiment and presents the experimental data and analysis results.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2016.12.010

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2016.12.010;
PII
S0029-5493(16)30492-7;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
313
Journal Page Range
p. 129-140
ISSN
0029-5493
CODEN
NEDEAU

Optional Information

Copyright
Copyright (c) 2016 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.