Journal
NUCLEAR SCIENCE AND ENGINEERING
Volume -, Issue -, Pages -Publisher
TAYLOR & FRANCIS INC
DOI: 10.1080/00295639.2023.2211191
Keywords
Radiation protection; Monte Carlo; FLUKA; Large Hadron Collider; CERN
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This paper summarizes the use of Monte Carlo radiation transport codes in estimating radionuclide production yields and activities for radiological characterization studies at high-energy accelerator facilities like CERN. It presents the principles of the fluence conversion coefficients method and showcases its practical application through Monte Carlo simulations for the upcoming pilot beam run at the Large Hadron Collider. The flexibility of the method and its operational radiation protection implications are also discussed.
At high-energy accelerator facilities like the ones that are part of the accelerator complex at the European Organization for Nuclear Research (CERN), Monte Carlo radiation transport codes are widely employed to face the challenges of estimating radionuclide production yields and activities with the aim of performing the radiological characterization of activated components. Indeed, it is of paramount importance to ensure adequate radiation protection during scheduled maintenance, transport, and handling of these components and to establish their proper disposal pathway once they ultimately reach the end of their useful life. This paper summarizes the principles of the fluence conversion coefficients method that was developed as a complementary approach for radiological characterization studies. Then, the Monte Carlo simulations in preparation to the pilot beam run at the Large Hadron Collider at CERN in 2021 are presented as a practical example of possible applications. Finally, the flexibility of the method and the most relevant operational radiation protection implications are discussed in relation to the provided example.
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