Development and Verification of the Dynamic System Code THERMO-T for Research Reactor Accident Analysis-Reference-Cited by-同舟云学术

Development and Verification of the Dynamic System Code THERMO-T for Research Reactor Accident Analysis

Published:2016-11 Issue:2 Volume:196 Page:377-395
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Margulis Marat¹,Gilad Erez¹

Affiliation:

1. Ben-Gurion University of the Negev, Unit of Nuclear Engineering, Beer-Sheva 84105, Israel

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT16-23

Reference17 articles.

1. “IAEA Research Reactor Data Base,” International Atomic Energy Agency (2015).

2. “Use and Development of Coupled Computer Codes for the Analysis of Accidents at Nuclear Power Plants,” IAEA-TECDOC-1539, International Atomic Energy Agency (2007).

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. A hybrid machine learning approach for improving fuel temperature prediction of research reactors under mix convection regime;Results in Engineering;2022-09

2. High-Fidelity Steady-State and Transient Simulations of an MTR Research Reactor Using Serpent2/Subchanflow;Energies;2022-02-19

3. Advanced gas-cooled reactors technology for enabling molten-salt reactors design – Optimisation of a new system;Nuclear Engineering and Design;2021-12

4. Extension and validation of the SubChanFlow code for the thermo-hydraulic analysis of MTR cores with plate-type fuel assemblies;Nuclear Engineering and Design;2021-08

5. Simulations of SPERT-IV D12/15 transient experiments using the system code THERMO-T;Progress in Nuclear Energy;2018-11