ASTEC code DBA analysis of a passive mitigation strategy on a generic IRIS SMR-Reference-Cited by-同舟云学术

ASTEC code DBA analysis of a passive mitigation strategy on a generic IRIS SMR

Published:2021-06 Issue: Volume:156 Page:108194
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Maccari Pietro,Mascari Fulvio,Ederli Stefano,Meloni Paride,Manservisi Sandro

Funder

Institut de Radioprotection et de SÛreté Nucléaire

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference48 articles.

1. OECD, IEA, 2016. Energy and Air Pollution: World Energy Outlook Special Report 2016.

2. Analysis of primary/containment coupling phenomena characterizing the MASLWR design during a SBLOCA scenario;Mascari;Nuclear Power Plants. InTech.,2012

3. IAEA, 2014. Advances in small modular reactor technology developments, A Supplement to: IAEA Advanced Reactors Information System (ARIS) Vienna, https://aris.iaea.org/Publications/IAEA_SMR_Booklet_2014.pdf

4. Budnitz, Robert J., H-Holger Rogner, Adnan Shihab-Eldin, 2018. Expansion of nuclear power technology to new countries–SMRs, safety culture issues, and the need for an improved international safety regime, Energy policy,119, 535-544.

5. Technology readiness assessment of small modular reactor (SMR) designs;Liu;Prog. Nucl. Energy,2014

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

1. GOTHIC and MELCOR benchmarking of the CNL strong condensation containment apparatus experiments;Nuclear Engineering and Design;2024-10

2. Nuclear safety Enhanced: A Deep dive into current and future RAVEN applications;Nuclear Engineering and Design;2024-10

3. Severe accident analysis induced by secondary pipeline break in a small modular PWR;Nuclear Engineering and Technology;2024-10

4. An iPWR MELCOR 2.2 Study on the Impact of the Modeling Parameters on Code Performance and Accident Progression;Energies;2024-07-04

5. Development of an on-demand flooding safety system achieving long-term inexhaustible cooling of small modular reactors employing metal containment vessel;Nuclear Engineering and Technology;2024-07