2018
DOI: 10.1088/1742-6596/962/1/012044
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Neutron Fluence And DPA Rate Analysis In Pebble-Bed HTR Reactor Vessel Using MCNP

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Cited by 7 publications
(2 citation statements)
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“…This structure is a spectrum of 80 thermal, 47 epithermal, and 45 fast neutron energies ranging from 1.10 × 10 1a. Data of neutron flux obtained from the MCNP tally were normalized to the SAFARI-1 reactor power using Equation 1 [10,11].…”
Section: Calculation Of Energy-dependent Fluxmentioning
confidence: 99%
“…This structure is a spectrum of 80 thermal, 47 epithermal, and 45 fast neutron energies ranging from 1.10 × 10 1a. Data of neutron flux obtained from the MCNP tally were normalized to the SAFARI-1 reactor power using Equation 1 [10,11].…”
Section: Calculation Of Energy-dependent Fluxmentioning
confidence: 99%
“…Calculation of the dose rate distribution is done using the MCNP program [2]. The Monte-Carlo technique of the MCNP program has been widely used to solve of various nuclear reactor problems, especially in complex geometry modeling [3,5]. The analysis of the dose rate distribution started from the modeling of the core, radiation shielding up to the reactor building according to the composition and geometry of each component.…”
Section: Introductionmentioning
confidence: 99%