J. Ródenas

Analysis of photoneutron spectra produced in medical accelerators

A complete method is presented for the evaluation of photoneutron spectra produced in linear accelerators for cancer radiotherapy. It consists of a computer simulation code based on the MCNP4B Monte Carlo code, in which the new routine GAMMAN was implemented, allowing the accurate study of photoneutron production in high Z elements. In addition an experimental method based on a passive bubble spectrometer allows direct measurements of the photoneutron spectrum at the patient plane, also under the photon beam. The results are presented both for a 15 MeV linac with a traditional collimator system and for an 18 MeV linac equipped with a multileaf collimator, used in conformational radiotherapy.

Validation of the MCNP code for the simulation of Ge-detector calibration

Abstract This work was performed at the Nuclear Engineering Department in the Polytechnic University of Valencia in collaboration with IBERDROLA in order to calibrate the gamma spectrometry equipment used in Cofrentes NPP. MCNP code based on the MC method was applied to simulate the detection process. The paper presents the validation of the MCNP code when it is used for the simulation of detector calibration. The code is validated by comparing the results of various simulations with laboratory measurements.

Monte carlo simulation of the compton scattering technique applied to characterize diagnostic x-ray spectra.

The quality control of x-ray tubes for medical radiodiagnostic services is very important for such devices. Therefore, the development of new procedures to characterize the x-ray primary beam is highly interesting in order to obtain an accurate assessment of the actual photon spectrum. The Compton scattering technique is very useful to determine x-ray spectra (in the 10-150 kVp range), avoiding a pile-up effect in the detector since a large room is not usually available to apply other techniques. In this work, this process has been simulated using a Monte Carlo code, MCNP 4C. Some geometrical models have been developed and different techniques have been studied in order to improve statistics and accuracy in the acquisition of Pulse Height Distribution (PHD). The effect of both the collimation of the primary beam and the scattering angle of the spectrometer has been analyzed. Results obtained using simulation models have been compared with experimental measurements.

Consistent generation and functionalization of one-dimensional cross sections for TRAC-BF1

A method of calculation of correct functionalized cross sections and diffusion coefficients for TRAC-BF1, based on the one-dimensional kinetic files of the tridimensional simulator SIMULATE-3, is developed. The method allows the user to obtain first the consistent one-dimensional cross sections, diffusion coefficients, and bucklings, which upon being inserted into TRAC-BF1 conserve the three-dimensional eigenvalues, the planar reaction rates, and the fast and thermal radially averaged fluxes at each axial node. This method also compensates for the differences between the thermal-hydraulic models of the three-dimensional simulator and the transient analysis code. The errors obtained with this method are very small.

Estimation of the activity generated by neutron activation in control rods of a BWR

Control rods are activated by neutron reactions into the reactor. The activation is produced mainly in stainless steel and its impurities. The dose produced by this activity is not important inside the reactor, but it has to be taken into account when the rod is withdrawn from the reactor. Activation reactions produced have been modelled by the MCNP5 code based on the Monte Carlo method. The code gives the number of reactions that can be converted into activity.

Analysis of the dose rate produced by control rods discharged from a BWR into the irradiated fuel pool

BWR control rods become activated by neutron reactions into the reactor. Therefore, when they are withdrawn from the reactor, they must be stored into the storage pool for irradiated fuel at a certain depth under water. Dose rates on the pool surface and the area surrounding the pool should be lower than limits for workers. The MCNP code based on the Monte Carlo method has been applied to model this situation and to calculate dose rates at points of interest.

Indoor radon measurements in the city of Valencia

The indoor radon risk in Valencia (Spain) was studied more than twenty years ago in two surveys using different methodologies and leading to contradictory results. We report here on new indoor radon measurements with the charcoal canister technique, which confirm the low average level of indoor radon in the city, with a geometrical mean of 24 Bq/m(3) and an arithmetic mean of 27 Bq/m(3).

Analysis of dose rates received around the storage pool for irradiated control rods in a BWR nuclear power plant

BWR control rods are activated by neutron reactions in the reactor. The dose produced by this activity can affect workers in the area surrounding the storage pool, where activated rods are stored. Monte Carlo (MC) models for neutron activation and dose assessment around the storage pool have been developed and validated. In this work, the MC models are applied to verify the expected reduction of dose when the irradiated control rod is hanged in an inverted position into the pool.

Dosimetric characterization of a brachytherapy applicator using MCNP5 modelisation and in-phantom measurements

A gynaecological applicator consisting of a metallic intra-uterine tube with a plastic vaginal applicator and an HDR Ir-192 source have been simulated with MCNP5 (Monte Carlo code). A solid phantom has been designed to perform measurements around the applicator with radiochromic films. The isodose curves obtained are compared with curves calculated with the F4MESH tally of MCNP5 with a good agreement. A pinpoint ionization chamber has been used to evaluate dose at some reference points.

Uncertainty analysis in MCNP5 calculations for brachytherapy treatment.

The Monte Carlo (MC) method can be applied to simulate brachytherapy treatment planning. The MCNP5 code gives, together with results, a statistical uncertainty associated with them. However, the latter is not the only existing uncertainty related to the simulation and other uncertainties must be taken into account. A complete analysis of all sources of uncertainty having some influence on results of the simulation of brachytherapy treatment is presented in this paper. This analysis has been based on the recommendations of the American Association for Physicist in Medicine (AAPM) and of the International Standard Organisation (ISO).