Published August 2015 | Version v1
Journal article

Preliminary tests of particle image velocimetry for the upper plenum of a scaled model of a very high temperature gas cooled reactor

  • 1. Department of Mechanical Engineering, Texas A&M University, 3123 TAMU, College Station, TX 77843 (United States)
  • 2. Department of Nuclear Engineering, Texas A&M University, 3133 TAMU, College Station, TX 77843 (United States)

Description

Highlights: •A 1/16th scaled VHTR facility was constructed and preliminary tests were performed. •PIV tests for natural convection jets was performed at statistically steady state. •1000 frames were sufficient to represent the average velocity field. •The turbulence intensity peaks at 41–45% as the jets mixed. •PIV flow rates were validated by an analytic flow rate and ultrasonic flowmeter. -- Abstract: The Very High Temperature Reactor (VHTR) is a Generation IV nuclear reactor that is currently under design. During the design process multiple studies have been performed to develop safety codes for the reactor. Two major accidents of interest are the Pressurized Conduction Cooldown (PCC), and the Depressurized Conduction Cooldown (DCC) scenario. Both involve loss of forced coolant to the core, except the latter involves a pressure loss in the main coolant loop. During normal operation a circulator pumps the coolant into the upper plenum and down through the core, but following a loss of forced coolant the natural convection causes the flow to reverse to go through the core into the upper plenum. Computer codes may be developed to simulate the phenomenon that occurs in a PCC or DCC scenario, but benchmark data is needed to validate the simulations; previously there were no experimental test facilities to provide this. This study will cover the design, construction, and preliminary testing of a 1/16th scaled model of a VHTR that uses Particle Image Velocimetry (PIV) for flow visualization in the upper plenum. Three tests were run for a partially heated core at statistically steady state, and PIV was used to generate the velocity field of three naturally convective adjacent jets; the turbulent mixing of the jets was observed. After performing a sensitivity analysis the flow rate of a single pipe was extracted from the PIV flow field, and compared with an ultrasonic flowmeter and analytic flow rate. All the values lied within the uncertainty ranges, validating the test results.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.pnucene.2015.04.004

Additional details

Identifiers

DOI
10.1016/j.pnucene.2015.04.004;
PII
S014919701500092X;

Publishing Information

Journal Title
Progress in Nuclear Energy
Journal Volume
83
Journal Page Range
p. 305-317
ISSN
0149-1970

Optional Information

Notes
Copyright © 2015 Elsevier Ltd. All rights reserved.