THE NEUTRONICS OF INCREASED POWER DENSITY PWR CORE BASED ON ANNULAR FUEL RODS USING THE MONTE CARLO METHOD
DOI:
https://doi.org/10.66411/jer.v16i.224Keywords:
Power Density, Neutronics, Reactivity Control, Criticality, Flux, Brain Tumor, Annular Fuel, MCNP Code, PWR, Monte CarloAbstract
In this study the design parameters of the annular fuel cell are investigated and verified using the Monte Carlo method. The annular design shows a comparable neutronic performance to the solid fuel design as the difference in the infinite multiplication factor ( k∞ ) is far less than 1% and the difference from published work is within 1% [1]. This new design concept of annular fuel pins arranged in a 13 by 13 fuel assemblies has been suggested first at the Massachusetts Institute of Technology (MIT) where they have claimed a 150% power increase (3411 to 5111 MWt) without affecting the thermal and safety margins. Having established the confidence in the fuel cell design parameters, a detailed assembly and core model is described. The difficult part of the procedure is the Gadolinium burnable poison management where not all rods are poisoned and not all have the same mass fraction besides that some assemblies have highly enriched fuel rods and others have low enrichment ones. This lengthy iterative process is conditioned by less power fluctuations and by having enough amount of negative reactivity to cancel out the excess reactivity required for the fuel to deplete. The remaining 9% of excess reactivity is matched by 370 ppm of soluble boron to make the core critical. Therefore the X-Y fast and thermal flux and power map of the core and assembly in addition to axial power profiles in the core and hottest and average assembly and the hottest
References
[1] Kazimi M.S., Hejzlar P., “High Performance Fuel Design For Next Generation PWRs: Final Report,” January 2006. Massachusetts Institute of Technology
[2] Broiesmeister J.F., "MCNP" A Monte Carlo N-Particle transport code, technical report, CA-12625-M, LANL (1997)
[3] Zhiwen Xu, Design Strategies for Optimizing High Burnup Fuel in Pressurized Water Reactors. Massachusetts Institute of Technology, January 2003.
[4] Feng D., Kazimi, M. S. and Hejzlar, P. "Innovative Fuel Designs for High Power Density Pressurized Water Reactor," MIT-NFC-TR-075, September 2005.
[5] Kazimi, M. S. Hejzlar,P. et al., "High Performance Fuel Design for Next Generation PWRs: 4th Annual Report," MIT-NFC-PR-076, October 2005.
[6] Feng.D, Hejzlar P., and Kazimi M. S., “Thermal Hydraulic Design of High Power Density Fuel for Next Generation PWRs“, The 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10) Seoul, Korea, October 5- 9, 2003.
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