Invesigating the Stability of the Coolant Flow Ratein a Two-Circuit App With the SSP Wwer Reactor

Chistov, A. S.; Savikhin, O. G.; Ovchinnikov, V. F.; Nikolaev, M. Ya.

doi:10.32326/1814-9146-2015-77-3-309-318

Cited by 1 publication

(3 citation statements)

References 0 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The work (Chistov et al 2015) is focused on determining the instability region of the coolant flow rate in the first circulation circuit of a two-circuit NPP and in the second circuit of a steam generator (SG) for the nominal operating mode of the SCPS-600 reactor plant depending on the key parameters, as well as the region of flow stability in isolated parallel channels of the reactor core, taking into account the non-uniformity of heat release for different groups of fuel assemblies. The frequency and time analysis methods were used for a one-dimensional homogeneous model of the coolant flow.…”

Section: Results Of Thermal-hydraulic Stability Studiesmentioning

confidence: 99%

“…Based on the data in the table, we can note the following: of all the works, only two (Hou et al 2011, Chistov et al 2015 considered the features of the thermal-hydraulic stability of reactors, in which the coolant temperature at the inlet to the core exceeded the pseudocritical value at a given pressure.…”

Section: Summarizing Commentsmentioning

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%

See 2 more Smart Citations

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

Sujyan¹,

Deev²,

Kharitonov³

2021

NUCET

View full text Add to dashboard Cite

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.

show abstract

Section: Results Of Thermal-hydraulic Stability Studiesmentioning

confidence: 99%

Section: Summarizing Commentsmentioning

confidence: 99%