Application of best estimate thermal hydraulic code for safety analysis of high flux research reactor-Reference-Cited by-同舟云学术

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Application of best estimate thermal hydraulic code for safety analysis of high flux research reactor

Published:2017-06 Issue:2 Volume:6 Page:109-117
ISSN:2520-1352
Container-title:Life Cycle Reliability and Safety Engineering
language:en
Short-container-title:Life Cycle Reliab Saf Eng

Author:

Sengupta Samiran,Veluri Vijay K.,Patel R.,Mammen S.,Bhattacharya S.

Publisher

Springer Science and Business Media LLC

Subject

General Engineering

Link

http://link.springer.com/article/10.1007/s41872-017-0011-y/fulltext.html

Reference11 articles.

1. Bergles AE, Rohsenow WM (1964) The determination of forced convection surface boiling heat transfer. Trans ASME 86:365–372

2. Chafle SB, Sengupta S, Mukherjee P, Sasidharan K, Raina VK (2011) High flux research reactor. Thematic volume—reactor systems & applications. Bhabha Atomic Research centre, Mumbai, India, pp 195–200

3. Fuel Assemblies PSAR (2016) part-A, HFRR

4. Primary coolant system PSAR (2016) part-A, HFRR

5. Reactor Core Physics PSAR (2016) part-A HFRR

Cited by 2 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. Best Estimate Plus Uncertainty Analysis of Station Blackout Transient in Pool-Type Research Reactor;Nuclear Technology;2024-04

2. Thermal-Hydraulic Transient Analyses for Primary Coolant System of HFRR Using RELAP5;Nuclear Technology;2023-02-10

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