Passive cooling system in a nuclear spent fuel pool using a vertical straight wickless-heat pipe-Reference-Cited by-同舟云学术

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Passive cooling system in a nuclear spent fuel pool using a vertical straight wickless-heat pipe

Published:2018-04 Issue: Volume:126 Page:162-171
ISSN:1290-0729
Container-title:International Journal of Thermal Sciences
language:en
Short-container-title:International Journal of Thermal Sciences

Author:

Kusuma Mukhsinun Hadi,Putra Nandy,Antariksawan Anhar Riza,Koestoer Raldi Artono,Widodo Surip,Ismarwanti Sri,Verlambang Brilian Tegar

Funder

DRPM Universitas Indonesia

Publisher

Elsevier BV

Subject

General Engineering,Condensed Matter Physics

Reference27 articles.

1. Impact of the Fukushima accident on tritium, radiocarbon and radiocesium levels in seawater of the western North Pacific Ocean: a comparison with pre-Fukushima situation;Povinec;J Environ Radioact,2017

2. Radiocesium distribution and fluxes in the typical Cryptomeria japonica forest at the late stage after the accident at Fukushima Dai-Ichi Nuclear Power Plant;Yoschenko;J Environ Radioact,2017

3. Heat pipes: theory, design and applications;Reay,2013

4. Heat exchangers based on low temperature heat pipes for autonomous emergency WWER cooldown systems;Sviridenko;Appl Therm Eng,2008

5. The thermal performance of a loop-type heat pipe for passively removing residual heat from spent fuel pool;Xiong;Nucl Eng Des,2014

Cited by 55 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. Numerical study and assessment of a novel combined passive cooling system for tank-in-pool reactors;Annals of Nuclear Energy;2024-11

2. Progress in passive spent fuel pool cooling system R&D based on heat pipe technology;Progress in Nuclear Energy;2024-10

3. Thermal dynamics aspect identification of loop heat pipe with capillary tube wick using nonlinear autoregressive exogenous neural network;Nuclear Engineering and Technology;2024-07

4. Preliminary design and assessment of a novel passive residual heat removal system for the pool-vessel reactor system;Annals of Nuclear Energy;2024-06

5. Experimental investigation of the heat transfer characteristics, operating limits, and temperature distribution of a prototypically 3 m long two-phase closed thermosyphon for spent fuel pool passive cooling;Experimental and Computational Multiphase Flow;2024-05-15

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