Published June 2015 | Version v1
Journal article

Overview of methods to increase dryout power in CANDU fuel bundles

  • 1. University of Ottawa, Department of Mechanical Engineering, Ottawa (Canada)
  • 2. Chalk River Laboratories, AECL, Chalk River (Canada)
  • 3. Korean Atomic Energy Research Institute, Daejeon (Korea, Republic of)

Description

Highlights: • Small changes in bundle geometry can have noticeable effects on the bundle CHF. • Rod spacing devices can results in increases of over 200% in CHF. • CHF enhancement decays exponentially downstream from spacers. • CHF-enhancing bundle appendages also increase the post-CHF heat transfer. - Abstract: In CANDU reactors some degradation in the CCP (critical channel power, or power corresponding to the first occurrence of CHF in any fuel channel) will occur with time because of ageing effects such as pressure-tube diametral creep, increase in reactor inlet-header temperature, increased hydraulic resistance of feeders. To compensate for the ageing effects, various options for recovering the loss in CCP are described in this paper. They include: (i) increasing the bundle heated perimeter, (ii) optimizing the bundle configuration, (iii) optimizing core flow and flux distribution, (iv) reducing the bundle hydraulic resistance, (v) use of CHF-enhancing bundle appendages, (vi) more precise experimentation, and (vii) redefining CHF. The increase in CHF power has been quantified based on experiments on full-scale bundles and subchannel code predictions. The application of several of these CHF enhancement principles has been used in the development of the 43-rod CANFLEX bundle

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2015.03.010

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2015.03.010;
PII
S0029-5493(15)00116-8;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
287
Journal Page Range
p. 131-138
ISSN
0029-5493
CODEN
NEDEAU

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
47016379
Subject category
S42: ENGINEERING;
Descriptors DEI
AGING; CANDU TYPE REACTORS; CREEP; DECAY; DRYOUT; FORECASTING; FUEL ELEMENT CLUSTERS; GEOMETRY; HEAT TRANSFER; OPTIMIZATION; PRESSURE TUBES
Descriptors DEC
ENERGY TRANSFER; FUEL ASSEMBLIES; HEAVY WATER MODERATED REACTORS; MATHEMATICS; MECHANICAL PROPERTIES; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; THERMAL REACTORS; TUBES

Optional Information

Copyright
Copyright (c) 2015 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.