Evaluating the influence of radial power heterogeneity of fuel rod on its temperature in an accelerator driven subcritical system
Abstract
The radial non-uniformity of an ADS fuel rod power density on the peak plane is as high as 10.46 %, which is derived from the reactor physics calculations. In order to investigate the influence of the above-mentioned radial power inhomogeneity on the fuel temperature distribution, this paper constructs a set of two-dimensional comparison examples, where one example uses a uniform heat source and another uses a non-uniform heat source distribution, with taking the fuel segment and its corresponding cladding segment in the region where the peak plane is located as the research object. The finite element software COMSOL is used to conduct the heat transfer analysis. The results of the study show that the fuel temperature under radial non-uniform power distribution is almost the same as that under uniform power. Therefore, this radial non-uniformity can be completely ignored when the research object of temperature is considered. The quantitative calculation carried out in this research can provide certain data support for the engineering research of accelerator driven subcritical system, and can also provide certain guidance for the performance analysis of such fuel elements.
-
Author contributions: All the authors have accepted responsibility for the entire content of this submitted manuscript and approved submission.
-
Research funding: None.
-
Conflict of interest statement: The authors declare no conflicts of interest regarding this article.
References
Comsol (2021). COMSOL multiphysics reference manual 6.0. COMSOL AB, Stockholm.Suche in Google Scholar
Gu, L. and Su, X. (2021). Latest research progress for LBE coolant reactor of China initiative accelerator driven system project. Front. Energy 15: 810–831, https://doi.org/10.1007/s11708-021-0760-1.Suche in Google Scholar
Hales, J.D., Williamson, R.L., Novascone, S.R., Pastore, G., Spencer, B.W., Stafford, D.S., Gamble, K.A., Perez, D.M., Gardner, R.J., Liu, W., et al. (2016). BISON theory manual the equations behind nuclear fuel analysis. Idaho National Laboratory, Idaho.10.2172/1374503Suche in Google Scholar
Luzzi, L., Lorenzi, S., Pizzocri, D., Rozzia, D., Aly, A., and Del Nevo, A. (2014). Modeling and analysis of nuclear fuel pin Behavior for innovative lead cooled FBR. ENEA, Roma.Suche in Google Scholar
Li, J., Dai, Y., Gu, L., Zhang, Y., He, Z., Xu, H., Yao, C., Yu, R., Zhang, L., and Wang, D. (2021). Genetic algorithm based temperature control of the dense granular spallation target in China initiative accelerator driven system. Ann. Nucl. Energy 154: 108127, https://doi.org/10.1016/j.anucene.2021.108127.Suche in Google Scholar
Liu, R., Zhou, W., Prudil, A., and Chan, P.K. (2016). Multiphysics modeling of UO2-SiC composite fuel performance with enhanced thermal and mechanical properties. Appl. Therm. Eng. 107: 86–100, https://doi.org/10.1016/j.applthermaleng.2016.06.173.Suche in Google Scholar
Luo, P., Wang, S., Hu, Z., Xu, H., and Zhan, W. (2016). Accelerator driven sub-critical systems – a promising solution for cycling nuclear fuel. Physics 45: 569–577, https://doi.org/10.7693/wl20160903.Suche in Google Scholar
Liu, R., Zhou, W., Shen, P., Prudil, A., and Chan, P.K. (2015). Fully coupled multiphysics modeling of enhanced thermal conductivity UO2-BeO fuel performance in a light water reactor. Nucl. Eng. Des. 295: 511–523, https://doi.org/10.1016/j.nucengdes.2015.10.019.Suche in Google Scholar
Luscher, W.G., Geelhood, K.J., and Porter, I.E. (2015). Material property correlations: comparisons between FRAPCON-4.0, FRAPTRAN-2.0, and MATPRO. Pacific Northwest National Laboratory, Washington.Suche in Google Scholar
Mohsen, M.Y.M., Abdel-Rahman, M.A.E., and Abdelghafar Galahom, A. (2022). Untraditional solution for enhancing the performance of U-20 % Zr metallic alloy as an ATF using liquid metal bonded gap. Kerntechnik 87: 640–650, https://doi.org/10.1515/kern-2022-0065.Suche in Google Scholar
Prudil, A., Lewis, B.J., Chan, P.K., and Baschuk, J.J. (2015). Development and testing of the FAST fuel performance code: normal operating conditions (Part 1). Nucl. Eng. Des. 282: 158–168, https://doi.org/10.1016/j.nucengdes.2014.09.036.Suche in Google Scholar
Peng, T., Gu, L., Wang, D., Li, J., Zhu, Y., and Qin, C. (2017). Conceptual design of subcritical reactor for China initiative accelerator driven system. At. Energy Sci. Technol. 51: 2235–2241, https://doi.org/10.7538/yzk.2017.51.12.2235.Suche in Google Scholar
Soo Lee, H., Kim, D.-J., Kim, D.-S., and Kim, D.R. (2020). Evaluation of thermomechanical behaviors of UO2-5 vol% Mo nuclear fuel pellets with sandwiched configuration. J. Nucl. Mater. 539: 152295, https://doi.org/10.1016/j.jnucmat.2020.152295.Suche in Google Scholar
Wang, Z., Yao, C., Qin, Z., Sun, J., Pang, L., Shen, T., Zhu, Y., Cui, M., and Kongfang, W. (2019). Materials for components in accelerator-driven subcritical system. Strategic Study of Chinese Academy of Engineering 21: 39–48, https://doi.org/10.15302/J-SSCAE-2019.01.006.Suche in Google Scholar
Yu, R., Gu, L., Xin, S., Li, J., Zhu, Y., Zhang, L., and Jiang, W. (2021). Review of fuel assembly design in lead-based fast reactors and research progress in fuel assembly of China initiative accelerator driven system. Int. J. Energy Res. 45: 11552–11563, https://doi.org/10.1002/er.6569.Suche in Google Scholar
Zhan, W. and Xu, H. (2012). Advanced fission energy program-ADS transmutation system. Bull. Chin. Acad. Sci. 27: 375–381, https://doi.org/10.3969/j.issn.1000-3045.2012.03.017.Suche in Google Scholar
© 2023 Walter de Gruyter GmbH, Berlin/Boston
Artikel in diesem Heft
- Frontmatter
- An approach for an extension of the deflagration model in containment code system COCOSYS to separate burned and unburned atmosphere via junctions
- Neutronic analysis of the European sodium cooled fast reactor with Monte Carlo code OpenMC
- Identification and tracing of radionuclides in low- and medium-activity liquid radwaste sources of G.A. Siwabessy reactor
- Performance evaluation of a currently in-use dry storage cask design for spent accident tolerant fuel loading case under normal operation condition
- Optimization of divertor design for Pakistan spherical tokamak
- Role of impurity and thermal noise on the radiation sources in ITER using DT fuel
- An investigation of multistream plate-fin heat exchanger modelling and design: a review
- Ensuring safety of new, advanced small modular reactors for fundamental safety and with an optimal main heat transport systems configuration
- Study on calculation model and risk area of radionuclide diffusion in coastal waters under nuclear leakage accidents with different levels
- Optimization of 200 MWt HTGR with ThUN-based fuel and zirconium carbide TRISO layer
- Experimental study on boiling heat transfer of γ-Fe2O3 nanofluids on a downward heated surface
- Evaluating the influence of radial power heterogeneity of fuel rod on its temperature in an accelerator driven subcritical system
- Heat transfer enhancement of heat exchanger using rectangular channel with cavities
- Calendar of events
Artikel in diesem Heft
- Frontmatter
- An approach for an extension of the deflagration model in containment code system COCOSYS to separate burned and unburned atmosphere via junctions
- Neutronic analysis of the European sodium cooled fast reactor with Monte Carlo code OpenMC
- Identification and tracing of radionuclides in low- and medium-activity liquid radwaste sources of G.A. Siwabessy reactor
- Performance evaluation of a currently in-use dry storage cask design for spent accident tolerant fuel loading case under normal operation condition
- Optimization of divertor design for Pakistan spherical tokamak
- Role of impurity and thermal noise on the radiation sources in ITER using DT fuel
- An investigation of multistream plate-fin heat exchanger modelling and design: a review
- Ensuring safety of new, advanced small modular reactors for fundamental safety and with an optimal main heat transport systems configuration
- Study on calculation model and risk area of radionuclide diffusion in coastal waters under nuclear leakage accidents with different levels
- Optimization of 200 MWt HTGR with ThUN-based fuel and zirconium carbide TRISO layer
- Experimental study on boiling heat transfer of γ-Fe2O3 nanofluids on a downward heated surface
- Evaluating the influence of radial power heterogeneity of fuel rod on its temperature in an accelerator driven subcritical system
- Heat transfer enhancement of heat exchanger using rectangular channel with cavities
- Calendar of events