Code Validation of SAM Using Forced and Natural Circulation Data from NACIE-UP Benchmark-Reference-Cited by-同舟云学术

Code Validation of SAM Using Forced and Natural Circulation Data from NACIE-UP Benchmark

Published:2024-09-04 Issue: Volume: Page:1-16
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Coppo Leite Victor¹²^ORCID,Merzari Elia²^ORCID,Zou Ling³^ORCID

Affiliation:

1. Idaho National Laboratory, Nuclear Science and Technology Division, 955 MK Simpson Boulevard, Idaho Falls, Idaho 83415

2. Pennsylvania State University, Nuclear Engineering Department, 205 Hallowell Building, University Park, Pennsylvania 16802

3. Argonne National Laboratory, Nuclear Science and Engineering Division, 9700 S. Cass Avenue, Lemont, Illinois 60439

Publisher

Informa UK Limited

Link

https://www.tandfonline.com/doi/pdf/10.1080/00295450.2024.2377526

Reference36 articles.

1. C. BEHAR et al., “Technology Roadmap Update for Generation IV Nuclear Energy Systems,” Proc. OECD Nuclear Energy Agency for the Generation IV International Forum, Vol. 17, March 2014 (2014).

2. Overview of Lead-Cooled Fast Reactor Activities;ALEMBERTI A.;Prog. Nucl. Energy,2014

3. “Experimental Facilities in Support of Liquid Metal Cooled Fast Neutron Systems NP-T-1.15 in Nuclear Energy Series International Atomic Energy Agency (2018); https://www.iaea.org/publications/12245/experimental-facilities-in-support-of-liquid-metal-cooled-fast-neutron-systems.

4. F. ROELOFS et al., “2—Thermal-Hydraulic Challenges in Liquid-Metal-Cooled Reactors,” Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors, F. ROELOFS, Ed., pp. 17–43, Woodhead Publishing (2019); https://www.sciencedirect.com/science/article/pii/B9780081019801000028.

5. Analysis of turbulent flow and thermal structures in low-Prandtl number buoyant flows using direct numerical simulations