Verification of a novel fuel burnup algorithm in the RAPID code system based on Serpent-2 simulation of the TRIGA Mark II research reactor-Reference-Cited by-同舟云学术

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Verification of a novel fuel burnup algorithm in the RAPID code system based on Serpent-2 simulation of the TRIGA Mark II research reactor

Published:2023-10 Issue:10 Volume:55 Page:3732-3753
ISSN:1738-5733
Container-title:Nuclear Engineering and Technology
language:en
Short-container-title:Nuclear Engineering and Technology

Author:

Pungerčič Anže^ORCID,Mascolino Valerio^ORCID,Haghighat Alireza,Snoj Luka

Funder

Javna Agencija za Raziskovalno Dejavnost RS

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference55 articles.

1. Power peakings in mixed triga cores;Snoj;Nucl. Eng. Des.,2008

2. Nuclear Reactor Theory, Technical Report;Bell,1970

3. Dragon and cord-2 nuclear calculation of the npp krško fuel assembly;Kromar;Nucl. Eng. Des.,2012

4. Advanced Neutronics Methods for Analysis of the rbwr-ac;Hall,2013

5. Comparison of serpent and casmo-5m for pressurized water reactors models;Hursin,2013

Cited by 5 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. Experimental validation of the 3-D neutron kinetics algorithm of RAPID using the JSI TRIGA Mark-II reactor;Progress in Nuclear Energy;2024-11

2. JSI TRIGA fuel rod reactivity worth experiments for validation of Serpent-2 and RAPID fuel burnup calculations;Nuclear Engineering and Technology;2024-08

3. Development of a Predictor-Corrector Quasi-Static Transient Fission Matrix combination method for the neutronics transient simulation;Nuclear Engineering and Design;2024-08

4. The development of a high-performance combined fission matrix neutron transport and depletion coupled calculation;Progress in Nuclear Energy;2024-08

5. Analysis of Fission Matrix Databases with Nonuniform Fuel Temperature Profiles for Static and Transient Calculations;Nuclear Science and Engineering;2024-04-22

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