The HTR-10 (High Temperature Gas-cooled Test Reactor) is a 10 MW modular pebble bed type reactor, built by the Institute of Nuclear Energy Technology (INET), Tsinghua University, China. As an advanced reactor, it has good passive safety characteristics: capacity of retaining all fission products inside the coated particles (up to 1,600° C), passive decay heat removal, large heat capacity of the core to mitigate temperature transition, large fuel temperature margin and negative temperature reactivity coefficient sufficient to accommodate reactivity insertion and small amount of excess reactivity in the core. This reactor, which core is filled with 27,000 spherical fuel elements, e.g. TRISO coated particles, is used to test and develop fuel, verify PBR safety features, demonstrate combined electricity production and cogeneration of heat, and provide experience in PBR design, operation and construction. Using the SCALE 6.0 (Standardized Computer Analysis for Licensing Evaluation), the MCNPX 2.6.0 (Monte Carlo N-Particle eXtended) and the MCNP 5 (Monte Carlo N-Particle) nuclear codes, the HTR-10 first critical core described in the Evaluation of The Initial Critical Configuration of The HTR-10 Pebble-Bed Reactor was modeled and analyzed. A three-dimension model was simulated and the keff was obtained and compared with the reference. The result presents good agreement with experimental value. The goal is to validate the DEN/UFMG model to be applied in transmutation studies changing the fuel.
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2014 22nd International Conference on Nuclear Engineering
July 7–11, 2014
Prague, Czech Republic
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4593-6
PROCEEDINGS PAPER
A Neutronic Evaluation of the HTR-10 Using Scale, MCNPX and MCNP5 Nuclear Codes Available to Purchase
Rômulo V. Sousa,
Rômulo V. Sousa
Universidade Federal de Minas Gerais, Belo Horizonte, MG, Brazil
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Clarysson A. M. Silva,
Clarysson A. M. Silva
Universidade Federal de Minas Gerais, Belo Horizonte, MG, Brazil
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Ângela Fortini,
Ângela Fortini
Universidade Federal de Minas Gerais, Belo Horizonte, MG, Brazil
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Cláubia Pereira,
Cláubia Pereira
Universidade Federal de Minas Gerais, Belo Horizonte, MG, Brazil
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Maria Auxiliadora F. Veloso,
Maria Auxiliadora F. Veloso
Universidade Federal de Minas Gerais, Belo Horizonte, MG, Brazil
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Antonella L. Costa
Antonella L. Costa
Universidade Federal de Minas Gerais, Belo Horizonte, MG, Brazil
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Rômulo V. Sousa
Universidade Federal de Minas Gerais, Belo Horizonte, MG, Brazil
Clarysson A. M. Silva
Universidade Federal de Minas Gerais, Belo Horizonte, MG, Brazil
Ângela Fortini
Universidade Federal de Minas Gerais, Belo Horizonte, MG, Brazil
Cláubia Pereira
Universidade Federal de Minas Gerais, Belo Horizonte, MG, Brazil
Maria Auxiliadora F. Veloso
Universidade Federal de Minas Gerais, Belo Horizonte, MG, Brazil
Antonella L. Costa
Universidade Federal de Minas Gerais, Belo Horizonte, MG, Brazil
Paper No:
ICONE22-31128, V003T05A034; 5 pages
Published Online:
November 17, 2014
Citation
Sousa, RV, Silva, CAM, Fortini, Â, Pereira, C, Veloso, MAF, & Costa, AL. "A Neutronic Evaluation of the HTR-10 Using Scale, MCNPX and MCNP5 Nuclear Codes." Proceedings of the 2014 22nd International Conference on Nuclear Engineering. Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security. Prague, Czech Republic. July 7–11, 2014. V003T05A034. ASME. https://doi.org/10.1115/ICONE22-31128
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