ARIANT Assessments for CANDU Analysis Using RD-14M Experiments

Author:

Cui John1,Waddington Geoffrey1,Wang Shujun1,Liu Songyu1

Affiliation:

1. Canadian Nuclear Laboratories, Chalk River, Canada

Funder

CNL’s Laboratory-Directed Science and Technology

Publisher

Informa UK Limited

Reference7 articles.

1. N. U. AYDEMIR, “Recent Developments in CATHENA 4: A Fully-Implicit Network Thermalhydraulics Code,” Proc. 15th Int. Topl. Mtg. on Nuclear Reactor Thermal Hydraulics (NURETH-15), Pisa, Italy, May 12–15, 2013.

2. Comparing Coupled Multiphysics Simulations of Pump-Driven Transients for a Pressurized Heavy Water Reactor;BAZZANA S.;J. Nucl. Sci. Eng.,2024

3. N. U. AYDEMIR, “Application of the Relative Scaling Methodology to a CANDU-PHWR for the Power Pulse Phase,” Proc. 13th Int. Topl. Mtg. on Nuclear Reactor Thermal Hydraulics (NURETH-13), Kanazawa City, Ishikawa Prefecture, Japan, September 27–October 2, 2009.

4. J. CUI and G. WADDINGTON, “ARIANT Assessment Against RD-14M Small-Break Loss-of-Coolant Experiment,” Proc. Int. Conf. on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, Niagara Falls, Canada, August 13–17, 2023.

5. J. CUI and G. WADDINGTON, “ARIANT Assessment Against RD-14M Loss-of-Flow Experiment,” Proc. Int. Conf. on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, Niagara Falls, Canada, August 13–17, 2023.

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