Dose calculation in biological samples in a mixed neutron-gamma field at the TRIGA reactor of the University of Mainz

Authors

  • Tobias Schmitz Institute for Nuclear Chemistry, University of Mainz, D-55099 Mainz, Germany
  • Matthias Blaickner AIT Austrian Institute of Technology GmbH, 2444 Seibersdorf, Austria
  • Christian Schütz Institute for Nuclear Chemistry, University of Mainz, D-55099 Mainz, Germany
  • Norbert Wiehl Institute for Nuclear Chemistry, University of Mainz, D-55099 Mainz, Germany
  • Jens V. Kratz Institute for Nuclear Chemistry, University of Mainz, D-55099 Mainz, Germany
  • Niels Bassler Department of Experimental Clinical Oncology, Aarhus University Hospital, Aarhus, Denmark
  • Michael H. Holzscheiter Department of Physics & Astronomy, University of New Mexico, Albuquerque, NM 87131, USA; Max Planck Institute for Nuclear Physics, 69117 Heidelberg, Germany
  • Hugo Palmans National Physical Laboratory, Teddington TW11 0LW, Middlesex, UK
  • Peter Sharpe National Physical Laboratory, Teddington TW11 0LW, Middlesex, UK
  • Gerd Otto Department of Hepatobiliary, Pancreatic and Transplantation Surgery, University of Mainz, D-55131 Mainz, Germany
  • Gabriele Hampel Institute for Nuclear Chemistry, University of Mainz, D-55099 Mainz, Germany

DOI:

https://doi.org/10.3109/0284186X.2010.500306

Abstract

To establish Boron Neutron Capture Therapy (BNCT) for non-resectable liver metastases and for in vitro experiments at the TRIGA Mark II reactor at the University of Mainz, Germany, it is necessary to have a reliable dose monitoring system. The in vitro experiments are used to determine the relative biological effectiveness (RBE) of liver and cancer cells in our mixed neutron and gamma field. We work with alanine detectors in combination with Monte Carlo simulations, where we can measure and characterize the dose. To verify our calculations we perform neutron flux measurements using gold foil activation and pin-diodes. Material and methods. When L-α-alanine is irradiated with ionizing radiation, it forms a stable radical which can be detected by electron spin resonance (ESR) spectroscopy. The value of the ESR signal correlates to the amount of absorbed dose. The dose for each pellet is calculated using FLUKA, a multipurpose Monte Carlo transport code. The pin-diode is augmented by a lithium fluoride foil. This foil converts the neutrons into alpha and tritium particles which are products of the 7Li(n,α)3H-reaction. These particles are detected by the diode and their amount correlates to the neutron fluence directly. Results and discussion. Gold foil activation and the pin-diode are reliable fluence measurement systems for the TRIGA reactor, Mainz. Alanine dosimetry of the photon field and charged particle field from secondary reactions can in principle be carried out in combination with MC-calculations for mixed radiation fields and the Hansen & Olsen alanine detector response model. With the acquired data about the background dose and charged particle spectrum, and with the acquired information of the neutron flux, we are capable of calculating the dose to the tissue. Conclusion. Monte Carlo simulation of the mixed neutron and gamma field of the TRIGA Mainz is possible in order to characterize the neutron behavior in the thermal column. Currently we also speculate on sensitizing alanine to thermal neutrons by adding boron compounds.

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Published

2010-10-01

How to Cite

Schmitz, T., Blaickner, M., Schütz, C., Wiehl, N., Kratz, J. V., Bassler, N., … Hampel, G. (2010). Dose calculation in biological samples in a mixed neutron-gamma field at the TRIGA reactor of the University of Mainz. Acta Oncologica, 49(7), 1165–1169. https://doi.org/10.3109/0284186X.2010.500306

Issue

Vol. 49 No. 7 (2010): Acta Oncologica

Section

Articles