Author:
Bachrata A.,Trotignon L.,Sciora P.,Saez M.
Subject
Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Reference15 articles.
1. Alcouffe, R.E., Baker, R.S., Brinkley, F.W., Marr, D.R., O’Dell, R.D., Walters, W.F., 1995. DANTSYS: a diffusion accelerated neutral particle transport code system. LA-12969-M.
2. Bachrata, A., Bertrand, F., Lemasson, D., 2015. Unprotected Loss of Flow simulation on ASTRID CFV-V3 reactor core. In: Proceedings of ICAPP 2015, Nice, France, Paper 15356.
3. Conceptual design of ASTRID fuel assemblies;Beck;Nucl. Eng. Des.,2017
4. Comparison of the behaviour of two core designs for ASTRID in case of severe accidents;Bertrand;Nucl. Eng. Des.,2016
5. Status of severe accident studies at the end of the conceptual design of ASTRID: feedback on mitigation devices;Bertrand;Nucl. Eng. Des.,2017
Cited by
7 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