International Journal of Nuclear Energy

Research Article

Computational Model for the Neutronic Simulation of Pebble Bed Reactor’s Core Using MCNPX

Table 6

Results of B2 problem for both Original and Deviated benchmarks.
  B21 ( at 20°C or 27°C) B22 ( at 120°C) B23 ( at 250°C)
  T/D M T/D M T/D M
Original benchmark
China 1.1197 — 1.1104 — 1.0960 —
Germany11.13725 — 1.12404 — 1.10693 —
1.12665   1.11331 1.09588  
Indonesia21.2193 — 1.1983 — 1.1748 —
1.1381  1.1149  1.0844  
The Netherlands 1.1176 — 1.1085 —1.0963 —
Russia 1.1182 1.10761.1079 1.0933 1.0927 1.0794
Turkey3— 1.0941 — 1.0802 — 1.0671
  1.0809 1.0380  1.0035
USA4— 1.1319— 1.1279 — 1.1245
1.1298     
Our study 5— 1.1244— 1.1173 — 1.1067
Deviated benchmark
China 1.1358 1.1381 1.1262 — 1.1111 —
France6 —1.15679 — — — —
 1.14737    
Germany11.1468 — 1.1334 — 1.1160 —
1.1368  1.1232  1.1054  
South Africa 1.1286 — 1.1196 —1.1047  
Our study 5— 1.1332— 1.1256 — 1.1142
T/D: Transport or diffusion code.
M: Monte Carlo method based code.
1The first row of results was obtained with a VSOP bidimensional model and the second with a tridimensional VSOP model.
2The first row of results was obtained with DELIGHT code and the second with SRAC code.
3The first row of results was obtained with the Monte Carlo approximation using the ENDF/B-IV Nuclear Data Library and the second with the ENDF/B-V Nuclear Data Library.
4The first row of results was obtained with the Monte Carlo approximation using the UTXS Nuclear Data Library and the second with the ENDF/B-VI Nuclear Data Library.
5Results for B22 and B23 problems were obtained by polynomial interpolation.
6The first row of results was obtained with a homogeneous simplified model and the second with a heterogeneous improved model.