Shielding Assessment of the MYRRHA Accelerator-Driven System Using the MCNP Code
Abstract
The MYRRHA project includes the design and the development of an accelerator driven system (ADS) aimed at providing protons and neutrons for various R&D applications. With regard to the safety aspects, the assessment of the shielding and of the dose rates around the installation is an important task. In a first approach standard semi-empirical equations and attenuation factors found in the literature were applied. A more detailed determination of the neutron flux around the reactor is made here by Monte Carlo simulation with the code MCNP4B. The results of the shielding assessment give an estimate of the neutron flux at several positions around the core vessel and along the beam tube. Dose rates will be determined by applying the ICRP74 conversion factor.
- Publication:
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Advanced Monte Carlo for Radiation Physics
- Pub Date:
- 2001
- DOI:
- 10.1007/978-3-642-18211-2_148
- Bibcode:
- 2001amc..book..925C
- Keywords:
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- Physics