  |
In this work a detailed study of the annular fuel has been carried out. A thermal hydraulics code, ANUFAN (Annular Fuel Analysis), based on the bundle average method, capable of modeling both internally and externally cooled annular fuel pins is developed. Code predictions have been compared with calculations from Korea Atomic Energy Research Institute (KAERI) and MIT. Heat transfer fraction difference between ANUFAN and RELAP was found about 1.7%. Analysis of a 54 – fuel rod assembly is carried out with 36 and 45 numbers of annular fuel pins keeping the same channel size and bundle power as of the solid fuel assembly. Fuel pin maximum temperature of the annular fuel is found much less than the solid fuel. MCHFR value for annular fuel is found much higher compared to that of the solid fuel of 54 – fuel rod assembly. The full paper covers the details of the computer code, the analysis carried out and the results obtained.
From A. K. Vishnoi | D. K. Chandraker | P. K. Vijayan
(Received 23.06.2011)
Appeared in Kerntechnik 2012/01, Page 12-17
Direct link: http://www.nuclear-engineering-journal.com/KT110185
Pay content
Development of a thermal-hydraulic analysis code for annular fuel assemblies [389 KB]
This service is free for subscribers of Kerntechnik.
References
1 Kazimi, M. S. et al.: High performance Fuel Design for Next generation PWRs. NERI proposal, 2001.
2 Kim, H. T.; Hejzlar, P.; No, H. C.; Kazimi, M. S.: Performance of Internally and Externally Cooled Annular Fuel in a Loss of Coolant Accident. International Congress on Advanced Power Plants (ICAPP), Hollywood, Florida, June 2002.
3 Yang, Y. S.; Bae, M. K.; Shin, C. H.; Chun, T. H.; Bang, J.G.; Song, K.W.: Conceptual Design of OPR-1000 Compatible Annular Fuel Assembly. ICAPP 2007 Technical Program (as of 27 April 2007).
4 Han, H. K.; Chang, S. H.: Development of a thermal-hydraulic analysis code for annular fuel assemblies. Nuclear Engineering and Design 226 (2003) 267–275.
5 Zhao, J.; No, H. C.; Kazimi, M. S.: Mechanical analysis of high power internally cooled annular fuel. Nuclear Technology 146 (2004) 164–180.
6 Groeneveld, D. C.; Leung, L. K. H.; Kirillov, P. L.; Bobkov, V. P.; Smogalev, I. P.; Vinogradov, V. N., Huang, X. C.; Royer, E.: The 1995 look-up table for critical heat flux in tubes. Nuclear Engineering and Design 163 (1995) 1–23.
|
| © 2013 by Carl Hanser Verlag |
Navigation
- Current issue
- Volumes
- Search
- Sponsored articles
- Top 20 Downloads
Subscriber Support
abo-service@hanser.de
For authors:
Information on article submission
- Volumes
- Search
- Sponsored articles
- Top 20 Downloads
Subscriber Support
abo-service@hanser.de
For authors:
Information on article submission
Document number