Results 281 to 290 of about 3,602,304 (354)

Operation and safety analysis of space lithium-cooled fast nuclear reactor

Annals of Nuclear Energy, 2022
As the power requirements for deep space exploration continue to increase, space nuclear power systems are imperative. In this paper, a set of models are established for the lithium-cooled space reactor combined with the Stirling engine.
Zhao Jin, Chenglong Wang, Xiao Liu, Zhiwen Dai, W. Tian, G. Su, S. Qiu   +6 more
semanticscholar   +1 more source

CFD modelling of buoyancy driven flows in enclosures with relevance to nuclear reactor safety

Nuclear Engineering and Design, 2020
Nuclear reactor containment flows are primarily driven by density differences in the long term of a severe accident. It is crucial to predict such flows from the perspective of reactor safety.
G. Kumar, M. Kampili, S. Kelm, K. Prakash, H. Allelein   +4 more
semanticscholar   +1 more source

Nanofluid application for heat transfer, safety, and natural circulation enhancement in the NuScale nuclear reactor as a small modular reactor using computational fluid dynamic (CFD) modeling via neutronic and thermal-hydraulics coupling

, 2021
In recent years, “Nanofluid” and “Energy-Efficient Cooling” have been achieved growing attention for use in new nuclear reactor technology. Also, the assurance of reactor safety has become of top priority in nuclear energy development because of the ...
Z. Rahnama, G. Ansarifar
semanticscholar   +1 more source

Enhancing Tehran Research Reactor safety through a Second Shutdown System: A probabilistic safety assessment

Progress in Nuclear Energy, 2017
Ehsan Boustani, Samad Khakshournia
exaly   +2 more sources

HPR1000: Advanced Pressurized Water Reactor with Active and Passive Safety

Engineering, 2016
HPR1000 is an advanced nuclear power plant (NPP) with the significant feature of an active and passive safety design philosophy, developed by the China National Nuclear Corporation.
Ji Xing
exaly   +2 more sources

Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea

Nuclear Engineering and Technology, 2016
The Prototype Gen IV sodium cooled fast reactor (PGSFR) has been developed for the last 4 years, fulfilling the technology demonstration of the burning capability of transuranic elements included in light water reactor spent nuclear fuel.
Jae-Yong Lim, Sung Kyun Kim
exaly   +2 more sources

Studies on sodium aerosols dispersion in open environment for fast reactor safety

Annals of Nuclear Energy, 2019
In a sodium cooled Fast Reactors (SFRs), in the event of secondary sodium circuit failure (cracks developed in the fluid carrying pipe), the hot sodium is exposed to atmosphere, burns to produce sodium combustion aerosols and is released into the ...
V. Subramanian, Amit Kumar, Usha Pujala, P. Sujatha, C. Srinivas, A. Bagavathsingh, V. Goplakrishnan, R. Ananthanarayanan, A. Kumar, S. K. Kumar, S. Chandramouli, R. Baskaran, B. K. Nashine, B. Venkatraman   +13 more
semanticscholar   +1 more source

Enhanced thermal conductivity accident tolerant fuels for improved reactor safety – A comprehensive review

Annals of Nuclear Energy, 2018
UO 2 has a long history being used as a nuclear fuel. However, its low thermal conductivity has become one of the major concerns limiting nuclear reactor performance and safety. Enhanced thermal conductivity accident tolerant fuels have become one of the
Wei Zhou, Wenzhong Zhou
semanticscholar   +1 more source

Thermal-hydraulic and solid mechanics safety analysis for VVER-1000 reactor using analytical and CFD approaches

, 2020
Neutronic, thermal-hydraulics, and solid mechanics computations were used to study the different VVER-1000 reactors' operational conditions for the steady-state and the transient state.
M. M. Mohsen, Abdelfattah Y. Soliman, M. Abdel‐Rahman   +2 more
semanticscholar   +1 more source

Nuclear reactor safety

Dynamics and Control of Nuclear Reactors, 2019
Reactor safety is an important issue, deserving of a complete treatment. However, a full treatment is beyond the scope and purpose of this book. But all nuclear engineers need to know what can happen when things go bad.
T. Kerlin, B. Upadhyaya
semanticscholar   +1 more source