Investigation of Thermohydraulic Limits on Maximum Reactor Power in LEU Plate–Fueled, Pool-Type Research Reactor
Author:
Affiliation:
1. Purdue University, School of Nuclear Engineering, West Lafayette, Indiana 47906
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering
Link
https://www.tandfonline.com/doi/pdf/10.1080/00295639.2022.2055700
Reference43 articles.
1. J. JENKINS et al. “Analysis for the conversion of the Purdue University Research Reactor from HEU to LEU Fuel,” The RERTR International Meeting on Reduced Enrichment for Research and Test Reactors, Cape Town, Republic of South Africa, October 29 - November 2 (2006).
2. “Safety Evaluation Report for Renewal of the Facility Operating License for the PUR-1,” Purdue University (2016).
3. Onset of Nucleate Boiling in Research Reactors with Thin Rectangular Channels Under Low-Velocity Upward-Flow Conditions
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