What is it about?

Neutron shielding in fixed industrial radiography with Cf-252 source is a worldwide concern. The combination of iron, graphite, boron (or borate materials), and lead in this order, respectively, is the most appropriate shielding structure for an open Cf-252 source used in fixed industrial radiography. As iron is characterized by a high removal cross-section, its use in shielding the californium spontaneous neutron source is the key for shielding such facilities. The obtained results were confirmed with the Monte Carlo simulation-based Particle and Heavy Ion Transport code System (PHITS).

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Why is it important?

Our findings show that spontaneous neutron emitted from a Cf-252 source can be effectively shielded with common low-cost material. This will improve the use of neutron industrial radiography in developing countries where other effective neutron shielding materials as water poses structural problems (difficult to build a water wall in radiographic facilities).


This work leads to questioning the best Monte Carlo code for such evaluation. This will be developed using GEANT4 and a comparative study with PHITS is undertaken nowadays.

Dr Cebastien Joel GUEMBOU SHOUOP
Korea Advanced Institute of Science and Technology

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This page is a summary of: New Cf-252 neutron source shielding design based Monte Carlo simulation using material combination, AIP Advances, July 2020, American Institute of Physics, DOI: 10.1063/1.5144923.
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