Revisiting the QUENCH-11 integral reflood test with a new thermal–hydraulic model: Existence of a minimum injection rate-Reference-Cited by-同舟云学术

Revisiting the QUENCH-11 integral reflood test with a new thermal–hydraulic model: Existence of a minimum injection rate

Published:2012-11 Issue: Volume:49 Page:12-22
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Chikhi Nourdine,Fleurot Joelle

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference32 articles.

1. Amri, A., Clement, B., 2009. Joint OECD/NEA-EC/SARNET2 Workshop In-vessel Coolability. (CDROM), Issy-les-Moulineaux, France.

2. Berdyshev, A., Boldyrev, A., Palagin, A., Shestak, V., Veshchunov, M., 2001. Development of SVECHA/QUENCH Code for Modeling Fuel Cladding Degradation in QUENCH Tests. Tech. Rep. Paper 2028, Transactions SMiRT 16.

3. The physical closure laws in the CATHARE code;Bestion;Nuclear Engineering and Design,1990

4. A scenario of the Three Mile Island unit 2 accident;Broughton;Nuclear Technology,1989

5. Chatelard, P., Fleurot, J., Marchand, O., Drai, P., 2006. Assessment of the ICARE/CATHARE V1 severe accident code. In: Proceedings of ICONE 14, 14th International Conference on Nuclear Engineering. ASME, Miami, USA.

Cited by 6 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. References;Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors;2024

2. References;Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors;2024

3. References;Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors;2024

4. Modelling reflooding of intact core geometries in ASTEC V2.1: Improvements and validation on PERICLES experiments;Nuclear Engineering and Design;2021-07

5. Investigation of SAM measures during selected MBLOCA sequences along with Station Blackout in a generic Konvoi PWR using ASTECV2.0;Annals of Nuclear Energy;2017-07