CSR1000 single channel thermal hydraulic stability analysis using response matrix method
- 1. Beijing Key Laboratory of Passive Safety Technology for Nuclear Energy, North China Electric Power University, Beijing 102206 (China)
- 2. Institute of Nuclear Thermal-hydraulic Safety and Standardization, North China Electric Power University, Beijing 102206 (China)
- 3. North China Electric Power University, Nuclear Thermal Safety and Standardization Research Institute, Beijing 102206 (China)
Description
Highlights: •System response matrix method analyzes thermal-hydraulic stability of CSR1000. •Single channel analysis decouples neutronics from thermal-hydraulic analysis. •A modular code is presented to solve the system response matrix of CSR1000. •Stability is a function of system pressure, power, flow rate and number of nodes. •Inlet orifice plate can be designed to stabilize the reactor in steady operation. -- Abstract: To analyze the thermal-hydraulic stability of CSR1000 (a Chinese supercritical reactor), a Single Channel Thermal-Hydraulic Stability Analysis Code has been developed. This code follows the system response matrix method to determine the stability in time domain, by linearizing the perturbed conservation differential equations. The stability is represented as decay ratio, which is calculated axially at each node in the single channel. A parametric study is performed and it is found that system becomes stable by increasing mass flow rate and decreasing reactor power. The analysis becomes less sensitive for greater values of inlet orifice diameter ratios. The size of mesh has a great effect on the results of analysis. Increasing the system pressure also tends to stabilize the reactor. Using the results of this code, a method is devised to design and realize the concept of inlet orifice in CSR1000.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.pnucene.2016.04.007Additional details
Additional titles
- Augmented title (English)
- CSR1000;Thermal;Stability;Response
Identifiers
- DOI
- 10.1016/j.pnucene.2016.04.007;
- PII
- S0149197016300865;
Publishing Information
- Journal Title
- Progress in Nuclear Energy
- Journal Volume
- 91
- Journal Page Range
- p. 9-16
- ISSN
- 0149-1970
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51027765
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- DIFFERENTIAL EQUATIONS; FLOW RATE; MATRICES; ORIFICES; PARAMETRIC ANALYSIS; REACTIVITY; REACTOR OPERATION; RESPONSE MATRIX METHOD; STABILITY; THERMAL HYDRAULICS
- Descriptors DEC
- CALCULATION METHODS; EQUATIONS; FLUID MECHANICS; HYDRAULICS; MECHANICS; OPENINGS; OPERATION; REACTOR KINETICS EQUATIONS; REACTOR LIFE CYCLE
Optional Information
- Notes
- © 2016 Elsevier Ltd. All rights reserved.