A neutronic design was performed for 300 MWt Pressurized Water Reactor (PWR) with UO2 compacts made of coated fuel particles (CFP) comparing that with sintered pellets made of UO2 powder as ordinary fuel type. UO2 CFP type was enriched 4.8% of 235U and UO2 ordinary type was enriched 5% of 235U. Both reactors were operated with single batch refueling system with a cycle period of 3 years. The purpose of the design was to investigate the applicability of UO2 CFP type to PWR comparing with UO2 ordinary type that commonly used for PWR. The calculation was done with SRAC (Standard Reactor Analysis Code) computer code and nuclear library of JENDL-33. The results of calculation showed that k-effective for both type of fuel could be maintained at critical condition for 3 years operation without refueling. The k-effective and the Doppler coefficients have been calculated for all types of fuel at 600 K and 900 K degrees. The results of calculation showed that for all types of fuel Doppler coefficient was negative, which was good for inherent safety characteristic. The size optimization design showed that the active core dimensions of UO2 CFP type reactor was about 2 times larger than the UO2 ordinary type reactor.
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14th International Conference on Nuclear Engineering
July 17–20, 2006
Miami, Florida, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4245-2
PROCEEDINGS PAPER
Design Study of 300 MWt PWR Fueled With UO2 Coated Fuel Particle
Abu Khalid Rivai,
Abu Khalid Rivai
Tokyo Institute of Technology, Tokyo, Japan
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Ferhat Aziz,
Ferhat Aziz
National Nuclear Energy Agency, Jakarta, Indonesia
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Minoru Takahashi
Minoru Takahashi
Tokyo Institute of Technology, Tokyo, Japan
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Abu Khalid Rivai
Tokyo Institute of Technology, Tokyo, Japan
Ferhat Aziz
National Nuclear Energy Agency, Jakarta, Indonesia
Minoru Takahashi
Tokyo Institute of Technology, Tokyo, Japan
Paper No:
ICONE14-89287, pp. 593-597; 5 pages
Published Online:
September 17, 2008
Citation
Rivai, AK, Aziz, F, & Takahashi, M. "Design Study of 300 MWt PWR Fueled With UO2 Coated Fuel Particle." Proceedings of the 14th International Conference on Nuclear Engineering. Volume 4: Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition. Miami, Florida, USA. July 17–20, 2006. pp. 593-597. ASME. https://doi.org/10.1115/ICONE14-89287
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