Transient behavior of ASTRID with a gas power conversion system-Reference-Cited by-同舟云学术

Transient behavior of ASTRID with a gas power conversion system

Published:2016-11 Issue: Volume:308 Page:20-29
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Bertrand F.,Mauger G.,Bensalah M.,Gauthé P.

Funder

CEA

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference10 articles.

1. Comparison of the behaviour of two core designs for ASTRID in case of severe accidents;Bertrand;Nucl. Eng. Des.,2016

2. Cachon, L. et al., 2012. Innovative power conversion system for the French SFR prototype, ASTRID. In: Proceedings of ICAPP, Chicago, USA, June 24–28, 2012.

3. Status of ASTRID core design studies at the end of predesign phase 1;Chenaud;Nucl. Eng. Technol.,2013

4. Geffraye, G. et al., 2009. CATHARE 2 V2.5_2: a single version for various applications. In: The 13th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-13), Kanazawa City, Ishikawa Prefecture, Japan, September 27–October 2, 2009.

5. Laffont, G. et al., 2013. ASTRID power conversion system: assessment on steam and gas options. In: Proceedings of FR13, Paris, France, 4–7 March 2013, Paper CN-199-262.

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. Studies and cross-comparisons of severe accident prevention and mitigation capabilities of a SFR and a GFR;Nuclear Engineering and Design;2022-08

2. Exergoeconomic Analysis of a Novel Hybrid System by Integrating the Kalina and Heat Pump Cycles with a Nitrogen Closed Brayton System;Energy Reports;2021-11

3. Modeling of a cold thermal energy storage for the flexibility of thermal power plants coupled to Brayton cycles;Nuclear Engineering and Design;2021-01

4. Loss of off-site power transient analysis for a sodium-cooled fast reactor equipped with a gas power conversion system and preliminary optimisation of its operation;Nuclear Engineering and Design;2019-12

5. Determination of pressure loss coefficient of the hot duct break of the CEA ALLEGRO 2009 concept using a CFD technique;Nuclear Engineering and Design;2019-08