Published April 2018 | Version v1
Journal article

Impact of gap size uncertainty on calculated temperature uncertainty for the advanced gas reactor experiments

  • 1. Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID, 83415 (United States)

Description

Highlights: • Dimensional changes in compacts and holders during irradiation result in gap size changes. • Gap size uncertainty is among the most influential factors in temperature uncertainty. • Varying gap size models are based on dimensional measurements obtained during PIE. • PIE measurements reduce uncertainty in gap size and, subsequently, calculated temperature. - Abstract: Research being conducted on tristructural-isotropic fuel development and qualification involves seven advanced gas reactor (AGR) experiments that were planned to provide fuel qualification data to support the licensing and operation of the high-temperature gas-cooled reactor. Each AGR test consists of multiple independent capsules containing fuel compacts placed in one or more graphite cylinders shrouded by a stainless-steel shell. These capsules are instrumented with thermocouples embedded in the graphite holder, enabling temperature control. The desired fuel temperature is maintained by variation of the neon/helium gas mixture in response to feedback from thermocouple readings. In the absence of direct measurements, the commercial finite-element heat transfer code ABAQUS was used to predict fuel temperatures. Recognizing inherent uncertainties in the simulation model due to complex physical mechanisms, capsule geometries, and material properties, comprehensive temperature uncertainty quantification was performed. The uncertainty results reveal that the uncertainties in gap sizes are among the most influential factors contributing to calculated temperature uncertainty. The gap size uncertainties originate from a lack of direct experimental data for accurate assessment of dimensional change rates of fuel compacts and graphite components due to complex irradiation-induced material shrinkage or swelling. The study described here focuses on the impact of the gap size uncertainties based on the post-irradiation examination metrology data on calculated temperature uncertainty.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2017.08.009

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2017.08.009;
PII
S0029549317303849;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
329
Journal Page Range
p. 110-123
ISSN
0029-5493
CODEN
NEDEAU

Conference

Title
8. Topical Meeting on High Temperature Reactor Technology
Acronym
HTR 2016
Dates
6-10 Nov 2016
Place
Las Vegas, NV (United States)

Optional Information

Notes
© 2017 Elsevier B.V. All rights reserved.