1
|
Li T, Xiong J, Zhang T, Chai X, Liu X. Multi-physics coupled simulation on steady-state and transients of heat pipe cooled reactor system. ANN NUCL ENERGY 2023. [DOI: 10.1016/j.anucene.2023.109774] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 03/08/2023]
|
2
|
Huang M, Du Z, Liu Y, Peng C. Comparative study on peak power prediction methods during start-up and power-up of heat pipe reactor based on neural network and decision tree. NUCLEAR ENGINEERING AND DESIGN 2023. [DOI: 10.1016/j.nucengdes.2023.112208] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 02/12/2023]
|
3
|
Wang Z, Ye T, Guo K, Tian W, Qiu S, Su G. Molecular dynamics study of the wettability effect on the evaporation of thin liquid sodium film. NUCLEAR ENGINEERING AND DESIGN 2023. [DOI: 10.1016/j.nucengdes.2023.112183] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 02/08/2023]
|
4
|
Wu Y, Zheng Y, Tao Y, Liu X, Du X, Wang Y. The low-enriched uranium core design of a MW heat pipe cooled reactor. NUCLEAR ENGINEERING AND DESIGN 2023. [DOI: 10.1016/j.nucengdes.2023.112195] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 01/26/2023]
|
5
|
Guo Y, Su Z, Li Z, Yu J, Wang K. Research on the effect of heat pipe temperature oscillation on heat pipe cooled reactor operation. ANN NUCL ENERGY 2023. [DOI: 10.1016/j.anucene.2022.109587] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
|
6
|
Allaf M, Okamoto K, Suzuki S, Erkan N. Conceptualization of the micro research reactor cooled by heat pipes (MRR-HP), part-II: safety analyses. J NUCL SCI TECHNOL 2023. [DOI: 10.1080/00223131.2022.2159560] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 01/13/2023]
Affiliation(s)
- Mohammad Allaf
- Nuclear Professional School, The University of Tokyo, Tokyo, Japan
| | - Koji Okamoto
- Nuclear Professional School, The University of Tokyo, Ibaraki, Japan
| | - Shunichi Suzuki
- Nuclear Engineering and Management, The University of Tokyo, Tokyo, Japan
| | - Nejdet Erkan
- Fusion Technology Facility, United Kingdom Atomic Energy Authority (UKAEA), Rotherham, UK
| |
Collapse
|
7
|
Liu S, Kang M, Yuan Y, Huang Q, Du Z, He X, Zhou Y. Experimental study of explosion characteristics caused by High-Temperature sodium leakage from a heat pipe into air. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2022.109387] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
|
8
|
Surip W, Putra N, Antariksawan AR. Design of passive residual heat removal systems and application of two-phase thermosyphons: A review. PROGRESS IN NUCLEAR ENERGY 2022. [DOI: 10.1016/j.pnucene.2022.104473] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/21/2022]
|
9
|
Startup analyses of a megawatt heat pipe cooled reactor. PROGRESS IN NUCLEAR ENERGY 2022. [DOI: 10.1016/j.pnucene.2022.104405] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
|
10
|
Failure probability evaluation for a weld of the heat pipe in the Mega-Power heat pipe cooled reactor. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2022.109324] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/22/2022]
|
11
|
Wang C, Zhang Z, Zhang M, Li P, Tian Z, Tian W, Qiu S, Su G. Numerical evaluation of non-condensable gas influence on the heat transfer characteristics of high-temperature lithium heat pipe during reactor operation. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2022.109077] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
|
12
|
Liu L, Liu B, Xiao Y, Gu H, Guo H. Preliminary thermal and mechanical analysis on the reactor core of a new heat pipe cooled reactor applied in the underwater environment. PROGRESS IN NUCLEAR ENERGY 2022. [DOI: 10.1016/j.pnucene.2022.104306] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/18/2022]
|
13
|
Hedayat A. The role of advanced nuclear reactors in non-electrical and strategic applications, producing sustainable energy supplies and reducing the greenhouse gasses. KERNTECHNIK 2022. [DOI: 10.1515/kern-2022-0029] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/15/2022]
Abstract
Abstract
Nowadays, nuclear reactors became extremely fascinating not only for most of the nuclear communities but also for the prominent energy suppliers to fix the global warming effects worldwide. This paper presents a review of the last advances, applications, and challenges of nuclear reactors. Different types and classifications are introduced. Advantages and disadvantages are discussed for best decision-making. Next, nuclear safety is also discussed as the most important challenging subject to develop nuclear reactors worldwide. They are specially mentioned to find the key solution for the future of nuclear energy. A brief review of nuclear roadmaps is compared with other clean green technologies as well. Estimated prospects for projects timelines and progressions of new nuclear reactors are also presented and discussed briefly. Studies confirmed that nuclear reactors are not only required for developing non-electrical applications or even high-tech systems but also they are extremely profitable to restrict global warming effects. Finally, the solution is to enhance the markets of the nuclear reactors, especially the matured Gen III+ Pressurized Water Reactors (PWRs) to resolve short-term problems as well as advanced futuristic developing Small Modular Reactors (SMRs) for the mid-term and long-term strategies. Moreover, research reactors especially advanced Multi-Purpose Research Reactors (MPRR) are necessary tools to develop both nuclear power plants and other advanced technologies as well as the modern Micro Modular Reactors.
Collapse
Affiliation(s)
- Afshin Hedayat
- Reactor and Nuclear Safety Research School, Nuclear Science and Technology Research Institute (NSTRI) , End of North Karegar Street, P.O. Box: 14395-836 , Tehran , Iran
| |
Collapse
|
14
|
Zhang Y, Chai X, Wang C, Tang S, Zhang D, Tian W, Su G, Qiu S. Thermal-hydraulic analysis of heat pipe reactor experimental device with thermoelectric generators. PROGRESS IN NUCLEAR ENERGY 2022. [DOI: 10.1016/j.pnucene.2022.104137] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/19/2022]
|
15
|
Ma K, Hu P. Preliminary conceptual design and neutroncis analysis of a heat pipe cooled traveling wave reactor. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2021.108907] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
|
16
|
|
17
|
Ma Y, Han W, Xie B, Yu H, Liu M, He X, Huang S, Liu Y, Chai X. Coupled neutronic, thermal-mechanical and heat pipe analysis of a heat pipe cooled reactor. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2021.111473] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
|
18
|
Abstract
Blankets are a difficult problem for fusion engineering design. Because of the complex flow channels, the design, production, processing, and accident maintenance of blankets are all huge challenges for traditional water/gas-cooled blankets. Blankets are the bridge for heat transfer and tritium production. A high-performance blanket with simplified structure is obviously beneficial for engineering, safety, and the economy. In this study, gravity heat pipes instead of coolant flow channels are adopted to remove the heat. Compared with coolant-cooled systems, heat pipes may be simpler and more reliable. The in-vessel and in-box loss of coolant accident (LOCA) will not occur because there is no coolant in the blanket. Moreover, a damaged heat pipe may be replaced easily compared to a damaged water-cooled blanket. In this study, a hypothetical heat pipe-cooled blanket for the China Fusion Engineering Test Reactor (CFETR) was proposed and one module of the blanket was analyzed by numerical simulation. The results were compared with those of a water-cooled blanket, and the temperature distribution of the heat pipe-cooled blanket is more uniform. This study verified the preliminary feasibility of heat pipe-cooled blankets and provided a fresh idea for blanket design.
Collapse
|
19
|
Ma Y, Tian C, Yu H, Zhong R, Zhang Z, Huang S, Deng J, Chai X, Yang Y. Transient heat pipe failure accident analysis of a megawatt heat pipe cooled reactor. PROGRESS IN NUCLEAR ENERGY 2021. [DOI: 10.1016/j.pnucene.2021.103904] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
|
20
|
3D-2D coupling multi-dimension simulation for the heat pipe micro-reactor by MOOSE&SAM. PROGRESS IN NUCLEAR ENERGY 2021. [DOI: 10.1016/j.pnucene.2021.103790] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/21/2022]
|
21
|
Ma Y, Chen E, Yu H, Zhong R, Deng J, Chai X, Huang S, Ding S, Zhang Z. Heat pipe failure accident analysis in megawatt heat pipe cooled reactor. ANN NUCL ENERGY 2020. [DOI: 10.1016/j.anucene.2020.107755] [Citation(s) in RCA: 18] [Impact Index Per Article: 3.6] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/26/2022]
|