Validation of DRAGON5 and DONJON5 computer codes with CNPGS Unit-3 cycle-1 design calculations
Author:
Publisher
Elsevier BV
Subject
Waste Management and Disposal,Energy Engineering and Power Technology,Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering
Reference25 articles.
1. Coupling of neutronics and thermal-hydraulic codes for simulation of the MNSR reactor;Al Zain;Nucl. Sci. Eng.,2019
2. Validation of deterministic code DRAGON5 for the fuel depletion analysis of a PWR pin-cell benchmark;Al Zain;Radiat. Phys. Chem.,2021
3. Steady-state thermal-hydraulic analysis of the Moroccan TRIGA MARK II reactor by using PARET/ANL and COOLOD-N2 codes;Boulaich;Nucl. Eng. Des.,2011
4. Accuracy of a 2-level scheme based on a subgroup method for pressurized water reactor fuel assembly models;Canbakan;Ann. Nucl. Energy,2015
5. Validation of a subgroup method for pressurized water reactor fuel assembly models;Canbakan,2015
Cited by 2 articles. 订阅此论文施引文献 订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献
1. Validation of DDC-3D code system for neutronics and thermal-hydraulics coupling analysis using BEAVRS benchmark;Nuclear Engineering and Design;2024-12
2. Comprehensive feasibility assessment of cycle length extension for CNPGS Unit-3;Progress in Nuclear Energy;2023-12
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