International Journal of Nuclear Energy / 2014 / Article / Tab 5

Research Article

Sensitivity Analysis of the TRIGA IPR-R1 Reactor Models Using the MCNP Code

Table 5

Average neutron flux in the middle of central thimble.

Inserted control rodThermal neutron flux (×1012·cm−2·s−1)
Case  1Case  2Case  3Case  4

Shim9.26409.76349.60709.7285
Safety9.56239.61099.66039.6336
Regulating9.718110.02249.91719.9200
No rods9.727110.05209.92739.9469

Inserted control rodTotal neutron flux (×1012·cm−2·s−1)
Case  1Case  2Case  3Case  4

Shim19.367920.065120.172820.1664
Safety19.871919.878620.028720.2220
Regulating20.097920.519520.315920.7339
No rods20.283620.705920.365620.9112

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