Corrigendum to: Two-temperature homogenized model for steady-state and transient thermal analyses of a pebble with distributed fuel particles [Ann. Nucl. Energy 36 (2009) 448-457] (DOI:10.1016/j.anucene.2008.11.031);Two-temperature homogenized model for steady-state and transient thermal analyses of a pebble with distributed fuel particles

Annals of Nuclear Energy

Volumn 36, Issue 4, 2009, Pages 448-457

  Cho, Nam Zin ^a   Yu, Hui ^a   Kim, Jong Woon ^a  

^a Korea Advanced Institute of Science and Technology (KAIST)   (South Korea)

Author keywords

[No Author keywords available]

Indexed keywords

FUELS; GAS COOLED REACTORS; GRAPHITE; PEBBLE BED REACTORS; THERMOANALYSIS; TRANSIENT ANALYSIS;

FUEL TEMPERATURE; HIGH HETEROGENEITY; HOMOGENIZED MODEL; POINT-KINETICS MODELS; STEADY STATE AND TRANSIENTS; TEMPERATURE FEEDBACK; THERMAL CALCULATION; VERY-HIGH-TEMPERATURE GAS-COOLED REACTORS;

THERMAL CONDUCTIVITY;

EID: 62349117144     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.anucene.2009.10.016     Document Type: Erratum

References (13)

1. Brown F.B., and Martin W.R. Stochastic geometry capability in MCNP5 for the analysis of particle fuel. Ann. Nucl. Ener. 31 (2004) 2039
2. Carson J.K., Lovatt S.J., Tanner D.J., and Cleland A.C. Thermal conductivity bounds for isotropic porous materials. Int. J. Heat Mass Transfer. 48 (2005) 2150
3. Cho N.Z., and Yu H. Fine-lattice stochastic modeling of particle fuels in an HTGR unit fuel element. Trans. Am. Nucl. Soc. 92 (2005) 510
4. Cho N.Z., and Yu H. Two-temperature homogenized model for thermal analysis of a pebble with distributed fuel particles. Trans. Am. Nucl. Soc. 98 (2008) 539
5. Johnson J.R., Lebenhaft J.R., and Driscoll M.J. Burnup reactivity and isotopics of an HTGR fuel pebble. Trans. Am. Nucl. Soc. 85 (2001) 273
6. Kadak, A. C., Ballinger, R. G., Driscoll, M. J., Yip, S., Wilson, D. G., No, H. C., Wang, J., MacLean, H., Galen, T., Wang, C., Lebenhaft, J., Zhai, T., Petti, D. A., Terry, W. K., Gougar, H. D., Ougouag, A. M., Oh, C. H., Moore, R. L., Miller, G. K., Maki, J. T., Smolik, G. R., and Varacalle, D. J., 2000. Modular Pebble Bed Reactor Project: University Research Consortium Annual Report, INEEL/EXT-2000-01034, Idaho National Engineering & Environmental Laboratory.
7. Kose, S., Kilic, I., 2004. Analysis of reactivity induced accident for HTR-10. In: 2nd International Topical Meeting on High Temperature Reactor Technology, Beijing, China.
8. Oh C.H., Davis C., Siefken L., Moore R., No H.C., Kim J., Park G.C., Lee J.C., and Martin W.R. Development of Safety Analysis Codes and Experimental Validation for Very High Temperature Gas-Cooled Reactors, INL/EXT0601362 (2006), Idaho National Laboratory
9. Reitsma, F., Strydom, G., de Haas, H., Ivanov, K., Tyobeka, B., Mphahlele, R., Downar, T. J., Seker, V., Gougar, H. D., Da Cruz, D. F., Sikik, U.E., 2004. The PBMR steady-state and coupled kinetics core thermal-hydraulics benchmark test problems. In: 2nd International Topical Meeting on High Temperature Reactor Technology, Beijing, China.
10. Reitsma, F., Ivanov, K., Downar, T., de Haas, H., Sen, S., Strydom, G., Mphahlele, R., Tyobeka, B., Seker, V., Gougar, H. D., 2005. PBMR Coupled Neutronics/Thermal Hydraulics Transient Benchmark - The PBMR-400 Core Design, Benchmark Definition, Draft V03, NEA.
11. Shentu J., Yun S., and Cho N.Z. A Monte Carlo method for solving heat conduction problems with complicated geometry. Nuclear Engineering and Technology 39 (2007) 207. http://www.nuclear.or.kr/sub/04/sub_04_02.php (available on-line from Korean Nuclear Society at )
12. Song J.H., and Cho N.Z. Temperature distributions in a pebble with dispersed fuel particles calculated by Monte Carlo method. Trans. Am. Nucl. Soc. 98 (2008) 443
13. Song, J.H., and Cho, N.Z. An improved Monte Carlo method applied to the heat conduction analysis of a pebble with dispersed fuel particles. Nuclear Eng. Technol. (available on-line from Korean Nuclear Society at ).