Benchmarking nuclear data libraries against existing integral experiments for accelerator shielding applications

SCK•CEN Mentor

Çelik Yurdunaz,, +32 (0)14 33 21 96

Expert group

Nuclear Systems Physics

SCK•CEN Co-mentor

Stankovskiy Alexey , , +32 (0)14 33 21 88


MYRRHA (Multi-purpose hYbrid Research Reactor for High-tech Applications) is a flexible experimental lead-bismuth cooled accelerator driven system currently being developed at SCK•CEN. The linear accelerator of MYRRHA will accelerate the protons up to 600 MeV.  During routine operation of the accelerator, there will occur beam losses on the beam line structures. The interactions of the primary protons with the structural materials will produce a radiation field combining secondary protons, neutrons, photons, electrons, and other particles (depending on the incident beam energy) along the whole length of the beam line.

Shielding is required in order to protect workers, public, environment and equipment against prompt and delayed radiation. Attenuation of radiation to acceptable levels (below dose rate limit) can be achieved using shielding layers of appropriate materials and thickness. More accurate shielding design is based on calculation codes simulating the particle transport in matter and reliable nuclear data. Experimental shielding benchmark data can be used to improve  calculation model and to revise nuclear data for accelerator shielding calculations.


The  purpose of this internship is to test and validate the general purpose nuclear data libraries (JENDL, JEFF, ENDF, etc.) used for accelerator shielding applications. To benchmark cross section data library against existing integral experiments, the calculations will be compared with shielding experiments available in the SINBAD database. Two kinds of benchmark geometries were selected for validating nuclear data for the high energy accelerator shielding. These benchmarks contain transmission through shielding materials of neutrons and photons generated by 52 and 65 MeV proton beams. From this analysis of the calculation results for the benchmark with 52 MeV proton source it was concluded that proton nuclear data libraries have higher impact on the neutron production behind the shielding materials than the neutron libraries. In order to confirm the impact of the nuclear data libraries on the shielding results, a second experiment performed with 65 MeV protons is needed to be simulated.

The calculations will be performed with MCNPX Monte Carlo radiation transport code. The candidate is supposed to prepare MCNPX input files to model the selected experimental setup and prepare the suitable nuclear data libraries for the study. To complete the internship the candidate should write a detailed report describing the work and discussing the agreement or discrepancy of the calculations with experiments. The goal is to identify the most suitable nuclear data for each of the candidate shielding materials. The results should also be presented in an internal seminar.

The minimum diploma level of the candidate needs to be

Professional bachelor , Academic bachelor

The candidate needs to have a background in


Estimated duration

3 months