Radiation and Nuclear Physics Aspects of the Use of the Thorium Fuel Cycle in a Hybrid Fusion Facility-Reference-Cited by-同舟云学术

Radiation and Nuclear Physics Aspects of the Use of the Thorium Fuel Cycle in a Hybrid Fusion Facility

Published:2022-12-20 Issue:2 Volume:79 Page:117-134
ISSN:1536-1055
Container-title:Fusion Science and Technology
language:en
Short-container-title:Fusion Science and Technology

Author:

Titarenko Y. E.¹^ORCID,Ananev S. S.¹,Batyaev V. F.¹,Belousov V. I.¹,Blandinskiy V. Y.¹,Chernov K. G.¹,Davidenko V. D.¹,Dudnikov A. A.¹,Dyachkov I. I.¹,Ioannisian M. V.¹,Kovalishin A. A.¹,Khripunov V. I.¹,Kuteev B. V.¹,Legostaev V. O.¹,Malkov M. R.¹,Pavlov K. V.¹,Titarenko A. Y.¹,Zhigulina M. A.¹,Zhivun V. M.¹,Kashchuk Y. A.²,Meshchaninov S. A.²,Obudovsky S. Y.²,Stankovskiy A. Y.³,Konobeyev A. Y.⁴

Affiliation:

1. National Research Center, Kurchatov Institute, Moscow, 123182, Russia

2. JSC State Research Center of the Russian Federation, Troitsk Institute for Innovation and Fusion Research, Moscow, Troitsk, 108840, Russia

3. SCK CEN, Boeretang 200, B-2400 Mol, Belgium

4. Karlsruhe Institute of Technology, 76344 Eggenstein-Leopoldshafen, Germany

Funder

RFBR

Publisher

Informa UK Limited

Subject

Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics,Civil and Structural Engineering

Link

https://www.tandfonline.com/doi/pdf/10.1080/15361055.2022.2121525

Reference42 articles.

1. D. COLAMECO et al. “Tritium Technology Program Application,” Pacific Northwest National Laboratory, CASL Technical Symposium, February 19, 2020; https://caslmeetings.ornl.gov/wp-content/uploads/2019/05/10a-Colameco-CPNNL-SA-141058-TTP-Applications.pdf (current as of Feb. 12, 2019).

2. “Tritium Production Core (TPC),” Topical Report, Westinghouse Electric Company, NDP-98-181 (Rev.1), Feb. 8, 1999; https://www.nrc.gov/docs/ML1607/ML16077A093.pdf (current as of Feb. 8, 1999).

3. “Implementation and Utilization of Tritium Producing Burnable Absorber Rods (TPBARS) in Sequoyah Units 1 and 2,” FRAMATONE ANP, BAW-10237, September 2001; https://www.nrc.gov/docs/ML0127/ML012700190.pdf (current as of Sept. 19, 2001).

Cited by 3 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. Neutronic analysis of a tokamak hybrid blanket cooled by thorium-molten salt fuel mixture;Progress in Nuclear Energy;2024-09

2. Neutronic and thermohydraulic blanket analysis for hybrid fusion–fission reactor during operation;Nuclear Engineering and Technology;2023-07

3. MODEL RESEARCH OF MIXED CONVECTION IN MOLTEN SALTS FLOW WITH INFLUENCE OF DIFFERENT FORCES;Proceeding of International Heat Transfer Conference 17;2023