Flow instability analysis of supercritical water-cooled reactor CSR1000 based on frequency domain

Tian, Xiaogeng; Tian, Wenxi; Zhu, Dahuan; Qiu, Suizheng; Su, G.H.; Xia, Bangyang

doi:10.1016/j.anucene.2012.06.023

Cited by 14 publications

(2 citation statements)

References 17 publications

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“…In (Tian et al 2012), a study of the thermal-hydraulic stability of the CSR1000 reactor by the frequency analysis method using a one-dimensional numerical model is presented.…”

Section: Results Of Thermal-hydraulic Stability Studiesmentioning

confidence: 99%

“…Table 1. Purpose and main characteristics of computational models in works (Gómez et al 2008, Zhao et al 2007, Yi et al 2004a, Liu et al 2014, Hou et al 2011, Xiong et al 2013, Tian et al 2012, Yagov et al 2011, Chistov et al 2015, Su et al 2013, Dutta et al 2015a, Dutta et al 2015b, Yi et al 2004b, Buongiorno and MacDonald 2003, Zhao et al 2008 Particular consideration should be given to the development of one-dimensional models, in which the heat transfer between the coolant moving in the cells between the heat-generating and other elements of the core structure in non-stationary (transient) modes, when the heat capacity of materials can play a significant role.…”

Section: Summarizing Commentsmentioning

confidence: 99%

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Analysis of numerical studies on the thermal-hydraulic and neutronic thermal-hydraulic stability of supercritical water reactors

Sujyan¹,

Deev²,

Kharitonov³

2021

NUCET

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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.

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“…In (Tian et al 2012), a study of the thermal-hydraulic stability of the CSR1000 reactor by the frequency analysis method using a one-dimensional numerical model is presented.…”

Section: Results Of Thermal-hydraulic Stability Studiesmentioning

confidence: 99%