PuSH - Publication Server of Helmholtz Zentrum München: Pencil beam kernel-based dose calculations on CT data for a mixed neutron-gamma fission field applying tissue correction factors.

Navigation

Home

Deutsch

Research

Advanced Search

Browse by ...

... Journal

... Publication Type

... Research Data

... Publication Year

Publication overview

Support & Contact

Contact persons

Help

Data protection

Sommer, L.B.* ; Kampfer, S.* ; Chemnitz, T.* ; Breitkreutz, H.* ; Combs, S.E. ; Wilkens, J.J.*

Pencil beam kernel-based dose calculations on CT data for a mixed neutron-gamma fission field applying tissue correction factors.

Phys. Med. Biol. 69:045022 (2024)

DOI

Abstract
Metrics
Extra information

Objective. For fast neutron therapy with mixed neutron and gamma radiation at the fission neutron therapy facility MEDAPP at the research reactor FRM II in Garching, no clinical dose calculation software was available in the past. Here, we present a customized solution for research purposes to overcome this lack of three-dimensional dose calculation. Approach. The applied dose calculation method is based on two sets of decomposed pencil beam kernels for neutron and gamma radiation. The decomposition was performed using measured output factors and simulated depth dose curves and beam profiles in water as reference medium. While measurements were performed by applying the two-chamber dosimetry method, simulated data was generated using the Monte Carlo code MCNP. For the calculation of neutron dose deposition on CT data, tissue-specific correction factors were generated for soft tissue, bone, and lung tissue for the MEDAPP neutron spectrum. The pencil beam calculations were evaluated with reference to Monte Carlo calculations regarding accuracy and time efficiency. Main results. In water, dose distributions calculated using the pencil beam approach reproduced the input from Monte Carlo simulations. For heterogeneous media, an assessment of the tissue-specific correction factors with reference to Monte Carlo simulations for different tissue configurations showed promising results. Especially for scenarios where no lung tissue is present, the dose calculation could be highly improved by the applied correction method. Significance. With the presented approach, time-efficient dose calculations on CT data and treatment plan evaluations for research purposes are now available for MEDAPP.

Altmetric

Additional Metrics?

[➜Log in]

Edit extra informations Login

Publication type Article: Journal article

Document type Scientific Article

Corresponding Author

Keywords Fast Fission Neutron Therapy ; Fast Neutron Dose Calculation ; Fission Neutron Source ; Pencil Beam Kernel; Therapy; Medapp

ISSN (print) / ISBN 0031-9155

e-ISSN 1361-6560

Journal Physics in Medicine and Biology

Quellenangaben Volume: 69, Issue: 4, Article Number: 045022

Publisher Institute of Physics Publishing (IOP)

Publishing Place Bristol

Non-patent literature Publications

Reviewing status Peer reviewed

Institute(s) Institute of Radiation Medicine (IRM)

Grants German Research Foundation (DFG)
Deutsche Forschungsgemeinschafthttps://doi.org/10.13039/501100001659