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Radioactivity evaluation for the KSTAR tokamak
Hyunduk Kim1, Hee-Seock Lee, Sukmo Hong
1Pohang Accelerator Laboratory, POSTECH, Pohang 790-784, Korea.
Radiation Protection Dosimetry
|April 11, 2006
Summary
Neutron activation in the KSTAR tokamak creates radioactive materials, necessitating radiation protection measures. Tritium contamination in graphite tiles is a significant concern post-operation.
Area of Science:
- Nuclear Fusion Engineering
- Radiation Protection Physics
Background:
- The Korea Superconducting Tokamak Advanced Research (KSTAR) utilizes deuterium-deuterium (D-D) reactions, producing neutrons.
- Neutron irradiation of tokamak structures necessitates radiation protection assessments for post-shutdown work.
Purpose of the Study:
- To identify neutron-produced radionuclides in KSTAR.
- To evaluate absorbed dose in structural materials for radiation protection guidelines.
- To assess tritium contamination in plasma-facing components.
Main Methods:
- Neutron activation levels were calculated using MCNP4C2 and the FISPACT inventory code.
- Absorbed dose rates in the working area were estimated.
- Tritium production in graphite tiles was quantified.
Main Results:
- The absorbed dose in the inner vessel decreased to 4.26 x 10(-4) mrem/h 1.5 days post-shutdown.
- Tritium production in carbon graphite reached 3.03 x 10(6) Bq/kg.
- Neutron activation necessitates radiation safety protocols for tokamak maintenance.
Conclusions:
- Radiation protection assessments are crucial for safe tokamak operation and maintenance.
- Tritium accumulation in plasma-facing graphite requires specific handling procedures.
- Understanding neutron activation is key to managing radioactive environments in fusion devices.