Shielding design calculations for beam dump facility of KOMAC

Area of Science:

• Accelerator Physics
• Radiation Shielding
• Nuclear Engineering

Background:

• The Korea Multi-purpose Accelerator Complex (KOMAC) project aims to develop a high-intensity proton beam facility.
• Initial construction includes a 20 MeV linac by 2007, with upgrades to 100 MeV by 2012 using additional drift tube sections.

Purpose of the Study:

• To perform preliminary shielding estimates for the KOMAC facility.
• To evaluate gamma ray and neutron dose rates around the beam dump.
• To determine necessary shielding requirements for safe operation.

Main Methods:

• Utilized the three-dimensional (3-D) Monte Carlo transport code MCNPX for dose rate calculations.
• Performed tentative flux calculations using the 3-D deterministic code KATRIN.
• Compared results from MCNPX and KATRIN for validation.

Main Results:

• Preliminary shielding estimates, including gamma ray and neutron dose rates, were successfully calculated.
• Flux calculations were performed using both Monte Carlo and deterministic transport codes.
• Comparative analysis of MCNPX and KATRIN results provides confidence in the shielding estimations.

Conclusions:

• The study provides essential preliminary data for the radiation shielding design of KOMAC.
• The use of MCNPX and KATRIN codes ensures a robust approach to estimating shielding requirements.
• These findings are critical for ensuring the safety and successful construction of the accelerator complex.