Validating Intra-Plate Power Distributions in the Advanced Test Reactor
- 15 November 2021
- journal article
- research article
- Published by Taylor & Francis Ltd in Nuclear Technology
- Vol. 208 (5), 1-11
- https://doi.org/10.1080/00295450.2021.1980320
Abstract
The neutronics software, HELIOS, was validated in 2015 for performing core reload design and safety analysis of the Advanced Test Reactor. However, when HELIOS was benchmarked against historic fission-wire measurements (i.e., zero-power full-core measurements), a statistically resolved calculation-to-measurement bias was discovered. The azimuthal power along each fuel plate computed by HELIOS has consistently shown to underpredict measurements made by fission wires in historic zero-power tests near the fuel element side plates. It was hypothesized during the HELIOS software validation work that this bias is attributable to local moderation in coolant vents in the side plates axially just above and below the fission wires on the fuel plate edges. This work used detailed MCNP and MC21 models of the side plate vents to test this hypothesis. By comparing the average azimuthal biases between HELIOS and two-dimensional and three-dimensional (3-D) MCNP models and a 3-D MC21 model, it was found that the HELIOS azimuthal bias is not due to the measurement.Keywords
This publication has 8 references indexed in Scilit:
- Upgrading Limiting Peak-Power Analysis Techniques with Modern Validation and Uncertainty Quantification for the Advanced Test ReactorNuclear Technology, 2018
- A fission matrix based validation protocol for computed power distributions in the advanced test reactorNuclear Engineering and Design, 2015
- MC21 v.6.0 – A continuous-energy Monte Carlo particle transport code with integrated reactor feedback capabilitiesAnnals of Nuclear Energy, 2014
- Advanced Test Reactor Core Modeling Update Project: Annual Report for Fiscal Year 2014Published by Office of Scientific and Technical Information (OSTI) ,2014
- Advanced Test Reactor Core Modeling Update Project Annual Report for Fiscal Year 2013Published by Office of Scientific and Technical Information (OSTI) ,2013
- Power Distribution Analysis for the ORNL High Flux Isotope Reactor Critical Experiment 3Nuclear Science and Engineering, 2010
- Detailed MCNP Modeling of BR2 Fuel with Azimuthal VariationNuclear Technology, 2007
- CALCULATING REACTOR POWER FROM ACTIVATION TECHNIQUES AS APPLIED TO AN UNUSUAL FUEL GEOMETRY (ATRC).Published by Office of Scientific and Technical Information (OSTI) ,1967