1
|
Kumar G, Singh RK. Supercritical water flow in heated wire wrapped rod bundle channels: A review. PROGRESS IN NUCLEAR ENERGY 2023. [DOI: 10.1016/j.pnucene.2023.104620] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 02/23/2023]
|
2
|
Sujyan AM, Deev VI, Kharitonov VS. Analysis of numerical studies on the thermal-hydraulic and neutronic thermal-hydraulic stability of supercritical water reactors. NUCLEAR ENERGY AND TECHNOLOGY 2021. [DOI: 10.3897/nucet.7.78368] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022] Open
Abstract
The paper presents a review of modern studies on the potential types of coolant flow instabilities in the supercritical water reactor core. These instabilities have a negative impact on the operational safety of nuclear power plants. Despite the impressive number of computational works devoted to this topic, there still remain unresolved problems. The main disadvantages of the models are associated with the use of one simulated channel instead of a system of two or more parallel channels, the lack consideration for neutronic feedbacks, and the problem of choosing the design ratios for the heat transfer coefficient and hydraulic resistance coefficient under conditions of supercritical water flow. For this reason, it was decided to conduct an analysis that will make it possible to highlight the indicated problems and, on their basis, to formulate general requirements for a model of a nuclear reactor with a light-water supercritical pressure coolant. Consideration is also given to the features of the coolant flow stability in the supercritical water reactor core. In conclusion, the authors note the importance of further computational work using complex models of neutronic thermal-hydraulic stability built on the basis of modern achievements in the field of neutron physics and thermal physics.
Collapse
|
3
|
Shankar D, Pandey M, Basu DN. Parametric effects on coupled neutronic-thermohydraulic stability characteristics of supercritical water cooled reactor. ANN NUCL ENERGY 2018. [DOI: 10.1016/j.anucene.2017.10.008] [Citation(s) in RCA: 11] [Impact Index Per Article: 1.8] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
|
4
|
Zhao J, Saha P, Kazimi MS. Coupled Neutronic and Thermal-Hydraulic Out-of-Phase Stability of Supercritical Water-Cooled Reactors. NUCL TECHNOL 2017. [DOI: 10.13182/nt08-a4005] [Citation(s) in RCA: 10] [Impact Index Per Article: 1.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Jiyun Zhao
- Massachusetts Institute of Technology, Department of Nuclear Science and Engineering Center for Advanced Nuclear Energy Systems, 77 Massachusetts Avenue Cambridge, Massachusetts 02139
| | - Pradip Saha
- Massachusetts Institute of Technology, Department of Nuclear Science and Engineering Center for Advanced Nuclear Energy Systems, 77 Massachusetts Avenue Cambridge, Massachusetts 02139
| | - Mujid S. Kazimi
- Massachusetts Institute of Technology, Department of Nuclear Science and Engineering Center for Advanced Nuclear Energy Systems, 77 Massachusetts Avenue Cambridge, Massachusetts 02139
| |
Collapse
|
5
|
Zhao J, Tso CP, Tseng KJ. Nonhomogeneous-Nonequilibrium Two-Phase-Flow Model for Nuclear Reactor Single-Channel Stability Analysis. NUCL TECHNOL 2017. [DOI: 10.13182/nt12-a14520] [Citation(s) in RCA: 7] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Jiyun Zhao
- EXQUISITUS, Centre for E-City, School of Electrical and Electronics Engineering, Nanyang Technological University, Singapore
| | - C. P. Tso
- Nanyang Technological University, School of Mechanical and Aerospace Engineering, Division of Thermal and Fluids Engineering, Singapore
| | - K. J. Tseng
- EXQUISITUS, Centre for E-City, School of Electrical and Electronics Engineering, Nanyang Technological University, Singapore
| |
Collapse
|
6
|
Rahman MM, Dongxu J, Beni MS, Hei HC, He W, Zhao J. Supercritical water heat transfer for nuclear reactor applications: A review. ANN NUCL ENERGY 2016. [DOI: 10.1016/j.anucene.2016.06.022] [Citation(s) in RCA: 51] [Impact Index Per Article: 6.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
|
7
|
Saha P, Aksan N, Andersen J, Yan J, Simoneau J, Leung L, Bertrand F, Aoto K, Kamide H. Issues and future direction of thermal-hydraulics research and development in nuclear power reactors. NUCLEAR ENGINEERING AND DESIGN 2013. [DOI: 10.1016/j.nucengdes.2012.07.023] [Citation(s) in RCA: 20] [Impact Index Per Article: 1.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/27/2022]
|
8
|
Zhao J, Tso C, Tseng K. SCWR single channel stability analysis using a response matrix method. NUCLEAR ENGINEERING AND DESIGN 2011. [DOI: 10.1016/j.nucengdes.2011.04.026] [Citation(s) in RCA: 21] [Impact Index Per Article: 1.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/27/2022]
|