title: Ambient neutron dose equivalent outside concrete vault rooms for 15 and 18 MV radiotherapy accelerators.
abstract: In this work, the ambient dose equivalent, H*(10), due to neutrons outside three bunkers that house a 15- and a 18-MV Varian Clinac 2100C/D and a 15-MV Elekta Inor clinical linacs, has been calculated. The Monte Carlo code MCNPX (v. 2.5) has been used to simulate the neutron production and transport. The complete geometries including linacs and full installations have been built up according to the specifications of the manufacturers and the planes provided by the corresponding medical physical services of the hospitals where the three linacs operate. Two of these installations, those lodging the Varian linacs, have an entrance door to the bunker while the other one does not, although it has a maze with two bends. Various treatment orientations were simulated in order to establish plausible annual equivalent doses. Specifically anterior-posterior, posterior-anterior, left lateral, right lateral orientations and an additional one with the gantry rotated 30° have been studied. Significant dose rates have been found only behind the walls and the door of the bunker, near the entrance and the console, with a maximum of 12 µSv h(-1). Dose rates per year have been calculated assuming a conservative workload for the three facilities. The higher dose rates in the corresponding control areas were 799 µSv y(-1), in the case of the facility which operates the 15-MV Clinac, 159 µSv y(-1), for that with the 15-MV Elekta, and 21 µSv y(-1) for the facility housing the 18-MV Varian. A comparison with measurements performed in similar installations has been carried out and a reasonable agreement has been found. The results obtained indicate that the neutron contamination does not increase the doses above the legal limits and does not produce a significant enhancement of the dose equivalent calculated. When doses are below the detection limits provided by the measuring devices available today, MCNPX simulation provides an useful method to evaluate neutron dose equivalents based on a detailed description of linac, patient and bunker.
authors.affiliation: Grupo de Física Nuclear Aplicada y Simulación, Universidad Pedagógica y Tecnológica de Colombia, Tunja, Colombia.
authors.forename: S A
authors.initials: SA
authors.lastname: Martínez-Ovalle
authors.forename: R
authors.initials: R
authors.lastname: Barquero
authors.forename: J M
authors.initials: JM
authors.lastname: Gómez-Ros
authors.forename: A M
authors.initials: AM
authors.lastname: Lallena
mesh_terms: D000465:Algorithms; D003198:Computer Simulation; D004583:Electrons; D004867:Equipment Design; D006801:Humans; D009010:Monte Carlo Method; D009502:Neutrons; D016011:Normal Distribution; D010315:Particle Accelerators; D019047:Phantoms, Imaging; D011874:Radiometry / Q000379:methods*; D011878:Radiotherapy / Q000295:instrumentation* / Q000379:methods*; D011879:Radiotherapy Dosage