Prediction of the dynamical thermal behavior of a HTGR multilayered spherical fuel particle using lumped and distributed parameter models
Creators
- 1. Universidade Federal do Rio de Janeiro (UFRJ), RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia (COPPE). Programa de Engenharia Nuclear
Description
In this work, we studied the transient heat conduction in a coated fuel particle (TRISO). The analysis was carried out by using both the lumped parameter model and the distributed parameter model for comparison, which is solved by an implicit finite difference method. The lumped model approach requires lower computational efforts, allowing a fast evaluation of the average temperatures of all the five regions of the TRISO particle, while the distributed model approach provides an accurate evaluation of the approximate solution obtained by the lumped model. The two-point Hermite approximations for integrals were utilized in the lumped model approach for the average temperature and for the heat flux in each layer. For the average temperature, the plain trapezoidal rule (H0,0 approximation) and the two-side corrected first order trapezoidal rule (H1,1 approximation) were used in all layers, except for the innermost layer (UO2), where the second-order one-side corrected trapezoidal rule (H2,0 approximation) and the second-order two-side corrected trapezoidal rule (H2,1 approximation) were used. For the heat flux, the plain trapezoidal rule (H0,0 approximation) was utilized for all the layers. The finite difference solution employed 4001 points for the discretized dimension parameter and 50000 steps in time. The mechanical properties (thermal conductivity and specific heat) of the materials were supposed to be constant in function of the temperature and uniform in each region. (author)
Additional details
Publishing Information
- ISBN
- 978-85-99141-02-1
- Imprint Title
- Proceedings of the INAC 2007 International nuclear atlantic conference. Nuclear energy and energetic challenges for 21st. century. 15. Brazilian national meeting on reactor physics and thermal hydraulics; 8. Brazilian national meeting on nuclear applications
- Imprint Pagination
- [vp.]
- Journal Page Range
- [9 p.]
Conference
- Title
- INAC 2007 International nuclear atlantic conference. Nuclear energy and energetic challenges for 21st. century. 15. Brazilian national meeting on reactor physics and thermal hydraulics; 8. Brazilian national meeting on nuclear applications
- Dates
- 30 Sep - 5 Oct 2007
- Place
- Santos, SP (Brazil)
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 39084792
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data, Non-conventional Literature
- Descriptors DEI
- COATED FUEL PARTICLES; EXPERIMENTAL DATA; FINITE DIFFERENCE METHOD; HEAT FLUX; HTGR TYPE REACTORS; TEMPERATURE DEPENDENCE; THERMAL CONDUCTION; TRANSIENTS
- Descriptors DEC
- CALCULATION METHODS; DATA; ENERGY TRANSFER; FUEL PARTICLES; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HEAT TRANSFER; INFORMATION; ITERATIVE METHODS; MATHEMATICAL SOLUTIONS; NUMERICAL DATA; NUMERICAL SOLUTION; REACTORS
Optional Information
- Notes
- 21 refs., 3 figs., 2 tabs. Code: R02_761.pdf