The Minor Actinides (MA) generated by nowadays PWRs fleet has significant impact on environment and biosphere. Inert Matrix Fuels (IMF) is a possible way to reduce the production and hazard of MA in recent. From neutronic aspect, using the MCNP code with temperature related continuous neutron data, the present paper analyses the isotopic contributions to the Doppler Coefficients of certain types IMF fuels. It is concluded that, the Doppler Coefficients of Al2O3+ZrO2+MgO and ZrO2 based IMF fuels are much smaller than those containing ThO2, since the low neutron absorptions and lacking of resonance broadening of Al, Zr, Mg and O elements. For the same Inert Matrix, Reactor Grade Plutonium (RG-Pu) IMF fuels have more negative Doppler Coefficients than Weapon Grade Plutonium (WG-Pu) IMF fuels, which induce by the more abundance of resonance isotopes 240Pu, 242Pu in RG-Pu. Since the different neutron absorption cross-section profiles, the Er2O3 burnable poison has negative contribution to the Doppler Coefficient, however 10B, a typical 1/v absorber, is on the contrary way.
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2014 22nd International Conference on Nuclear Engineering
July 7–11, 2014
Prague, Czech Republic
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4594-3
PROCEEDINGS PAPER
Analysis of Isotopic Contributions to Doppler Coefficients of Inert Matrix Fuels
Jinsen Xie,
Jinsen Xie
University of South China, Hengyang, Hunan, China
China Institute of Atomic Energy, Beijing, China
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Tao Yu
Tao Yu
University of South China, Hengyang, Hunan, China
Search for other works by this author on:
Jinsen Xie
University of South China, Hengyang, Hunan, China
China Institute of Atomic Energy, Beijing, China
Tao Yu
University of South China, Hengyang, Hunan, China
Paper No:
ICONE22-30620, V004T11A009; 7 pages
Published Online:
November 17, 2014
Citation
Xie, J, & Yu, T. "Analysis of Isotopic Contributions to Doppler Coefficients of Inert Matrix Fuels." Proceedings of the 2014 22nd International Conference on Nuclear Engineering. Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory. Prague, Czech Republic. July 7–11, 2014. V004T11A009. ASME. https://doi.org/10.1115/ICONE22-30620
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