Radiation safety analysis for the A-BNCT facility in Korea.

A Proton Accelerator based Boron Neutron Capture Therapy (A-BNCT) facility is under development in Korea. Neutron beams for treatment are produced from a beryllium (Be) target and an 8 mA, 10 MeV proton beam. The purpose of the research is a radiation shielding analysis and an activation analysis for the facility design satisfying the radiation safety requirements as well as obtaining an operating license for the radiation facility according to a domestic nuclear commissioning procedure. The radiation shielding analysis was performed using the MCNPX computational particle transport code. The radiation source terms in the facility were evaluated and utilized in the shielding calculations. The minimum concrete thickness satisfying the designated dose rate of 5 µSv/h for the worker's area and 0.25 µSv/h for the public area were estimated and applied to the design. For an assessment of the radiation safety inside the facility, the dose rates were evaluated at several positions, such as behind the shielding door, around the primary barriers near the radiation sources, and in the penetrations of the ducts. The dose rate distribution was mapped for verification of the radiation safety for the entire facility. An activation analysis was carried out for the concrete walls, air, target assembly, beryllium target, and cooling water using FISPACT-2010 code. Concentrations of the activation products and dose rate induced by the radionuclides after shutdown were evaluated for the purpose of safe operation of the facility. The results were reviewed with the radiation safety regulations in Korea. As a result, it was proved that the final facility design satisfies the safety requirements.

Radiological safety concerns for the accelerator production of diagnostic and therapeutic radionuclides in a university setting.

Accelerator production of radionuclides for diagnostic and therapeutic research at a university has many advantages. Radionuclides not commonly available through commercial suppliers may be readily produced for innovative research applications. Loss of material due to decay in transit is minimized, and product lead times may be significantly reduced. Furthermore, graduate students and research assistants have the opportunity to gain considerable hands-on experience during the production, extraction, and processing operations. However, the benefits of implementing accelerator production into an existing radiological protection program must be balanced against increased safety procedures and maintenance of as-low-as-reasonably-achievable work practices. This article outlines the basics for radioactive material production and corresponding issues in radiological protection associated with the production, use, and disposal on a college campus.

An unrecognized occupancy change in the vicinity of a medical linear accelerator.

It seems obvious that if a significant increase in occupancy occurs in the immediate vicinity of any radiation room a reexamination of the adequacy of the shielding should be performed. We discuss a facility where a new building was constructed in close proximity to an existing medical linear accelerator and no consideration was given to the consequences of that construction as it might impact the doses received by occupants of the new structure. For more than 10 years some areas in that building may have received exposures greater than the allowed regulatory limit. The situation reported here should serve as a cautionary tale for those who have the responsibility for providing radiation protection at any site where new construction or increases in occupancy might require a reanalysis of the previously designed radiation shielding.

Neutron dose per fluence and weighting factors for use at high energy accelerators.

In June 2007, the United States Department of Energy incorporated revised values of neutron weighting factors into its occupational radiation protection regulation Title 10, Code of Federal Regulations Part 835, as part of updating its radiation dosimetry system. This has led to a reassessment of neutron radiation fields at high energy accelerators such as those at the Fermi National Accelerator Laboratory (Fermilab) in the context of the amended regulation and contemporary guidance of the International Commission on Radiological Protection (ICRP). Values of dose per fluence factors appropriate for accelerator radiation fields calculated elsewhere are collated and radiation weighting factors compared. The results of this revision to the dosimetric system are applied to americium-beryllium neutron energy spectra commonly used for instrument calibrations. Also, a set of typical accelerator neutron energy spectra previously measured at Fermilab are reassessed in light of the new dosimetry system. The implications of this revision and of recent ICRP publications are found to be of moderate significance.