Modelling of HTR (High Temperature Reactor) Pebble-Bed 10 MW to Determine Criticality as A Variations of Enrichment and Radius of the Fuel (Kernel) With the Monte Carlo Code MCNP4C

Hammam Oktajianto, Evi Setiawati, Very Richardina



Gas-cooled nuclear reactor is a Generation IV reactor which has been receiving significant attention due to many desired characteristics such as inherent safety, modularity, relatively low cost, short construction period, and easy financing. High temperature reactor (HTR) pebble-bed as one of type of gas-cooled reactor concept is getting attention. In HTR pebble-bed design, radius and enrichment of the fuel kernel are the key parameter that can be chosen freely to determine the desired value of criticality. This paper models HTR pebble-bed 10 MW and determines an effective of enrichment and radius of the fuel (Kernel) to get criticality value of reactor. The TRISO particle coated fuel particle which was modelled explicitly and distributed in the fuelled region of the fuel pebbles using a Simple-Cubic (SC) lattice. The pebble-bed balls and moderator balls distributed in the core zone using a Body-Centred Cubic lattice with assumption of a fresh fuel by the fuel enrichment was 7-17% at 1% range and the size of the fuel radius was 175-300 µm at 25 µm ranges. The geometrical model of the full reactor is obtained by using lattice and universe facilities provided by MCNP4C. The details of model are discussed with necessary simplifications. Criticality calculations were conducted by Monte Carlo transport code MCNP4C and continuous energy nuclear data library ENDF/B-VI. From calculation results can be concluded that an effective of enrichment and radius of fuel (Kernel) to achieve a critical condition was the enrichment of 15-17% at a radius of 200 µm, the enrichment of 13-17% at a radius of 225 µm, the enrichments of 12-15% at radius of 250 µm, the enrichments of 11-14% at a radius of 275 µm and the enrichment of 10-13% at a radius of 300 µm, so that the effective of enrichments and radii of fuel (Kernel) can be considered in the HTR 10 MW.

Keywords—MCNP4C, HTR, enrichment, radius, criticality



Criticality of reactor

Full Text:



DOE. 1993. Nuclear Physics and Reactor Theory. U S Department of Energy.

H. C. Kim, S. H. Kim, and J. K. Kim. 2011. A New Strategy to simulate a Random Geometry in A Pebble-Bed Core with The Monte Carlo Code MCNP. Sciencedirect journal.

Holbrook. 2008. NRC Licensing Strategy Development for the NGNP. Washington DC.

IAEA. 2003. Evaluation of High Temperature Gas Cooled Reactor Performance: Benchmark Analysis Related to Initial Testing of The HTTR and HTR-10. IAEA Publication.

J. F. Briesmeister. 1992. MCNP-A General Monte Carlo N-Particle Transport Code. Los Alomos National Laboratory.

Suwoto, Zuhair, and Mulyaman. 2010. Analisis Sensitivitas Parametik Dalam Perhitungan Kritikalitas Kisi Kernel Bahan Bakar RTT Menggunakan Program Monte Carlo MCNP5. Prosiding Seminar Nasional ke-16 Teknologi dan Keselamatan PLTN Serta Fasilitas Nuklir. pp. 189-196.

Volkan Şeker and Üner Ҫolak. 2002. HTR-10 full core first criticality analysis with MCNP. Sciencedirect journal.

W. Terry. 2006. Evaluation of the HTR-10 Reactor as a

Benchmark for Physics Code QA. Idaho National Laboratory.

Zuhair. 2012. Investigasi Kritikalitas HTR (High Temperature Reactor) Pebble Bed Sebagai Fungsi Radius dan Pengayaan Bahan Bakar Kernel. Indonesia Journal of Applied Physics. vol.2. pp. 146.

Published by Department of Chemical Engineering University of Diponegoro Semarang
Google Scholar

IJSE  by is licensed under Creative Commons Attribution 3.0 License.