scholarly journals The influence of nuclear models and Monte Carlo radiation transport codes on stray neutron dose estimations in proton therapy

2021 ◽  
pp. 106693
Author(s):  
M. De Saint-Hubert ◽  
J. Farah ◽  
M. Klodowska ◽  
M.T. Romero-Expósito ◽  
K. Tyminska ◽  
...  
2010 ◽  
Vol 37 (6Part21) ◽  
pp. 3273-3273 ◽  
Author(s):  
Y Zheng ◽  
E Klein ◽  
K Chen ◽  
Y Liu

Author(s):  
Keith T. Griffin ◽  
Tatsuhiko Sato ◽  
Sachiyo Funamoto ◽  
Konstantin Chizhov ◽  
Sean Domal ◽  
...  

AbstractThe radiation exposure estimates for the atomic bomb survivors at Hiroshima and Nagasaki have evolved over the past several decades, reflecting a constant strive by the Radiation Effects Research Foundation (RERF) to provide thorough dosimetry to their cohort. Recently, a working group has introduced a new series of anatomical models, called the J45 phantom series, which improves upon those currently used at RERF through greater age resolution, sex distinction, anatomical realism, and organ dose availability. To evaluate the potential dosimetry improvements that would arise from their use in an RERF Dosimetry System, organ doses in the J45 series are evaluated here using environmental fluence data for 20 generalized survivor scenarios pulled directly from the current dosimetry system. The energy- and angle-dependent gamma and neutron fluences were converted to a source term for use in MCNP6, a modern Monte Carlo radiation transport code. Overall, the updated phantom series would be expected to provide dose improvements to several important organs, including the active marrow, colon, and stomach wall (up to 20, 20, and 15% impact on total dose, respectively). The impacts were especially significant for neutron dose estimates (up to a two-fold difference) and within organs which were unavailable in the previous phantom series. These impacts were consistent across the 20 scenarios and are potentially even greater when biological effectiveness of the neutron dose component is considered. The entirety of the dosimetry results for all organs are available as supplementary data, providing confident justification for potential future DS workflows utilizing the J45 phantom series.


2007 ◽  
Vol 52 (15) ◽  
pp. 4481-4496 ◽  
Author(s):  
Yuanshui Zheng ◽  
Wayne Newhauser ◽  
Jonas Fontenot ◽  
Phil Taddei ◽  
Radhe Mohan

2015 ◽  
Vol 67 (1) ◽  
pp. 142-146 ◽  
Author(s):  
Jin Sung Kim ◽  
Jung Suk Shin ◽  
Daehyun Kim ◽  
Eunhyuk Shin ◽  
Kwangzoo Chung ◽  
...  

PLoS ONE ◽  
2017 ◽  
Vol 12 (10) ◽  
pp. e0186544
Author(s):  
Chaeyeong Lee ◽  
Sangmin Lee ◽  
Seung-Jae Lee ◽  
Hankyeol Song ◽  
Dae-Hyun Kim ◽  
...  

2014 ◽  
Vol 6 (1) ◽  
pp. 1006-1015
Author(s):  
Negin Shagholi ◽  
Hassan Ali ◽  
Mahdi Sadeghi ◽  
Arjang Shahvar ◽  
Hoda Darestani ◽  
...  

Medical linear accelerators, besides the clinically high energy electron and photon beams, produce other secondary particles such as neutrons which escalate the delivered dose. In this study the neutron dose at 10 and 18MV Elekta linac was obtained by using TLD600 and TLD700 as well as Monte Carlo simulation. For neutron dose assessment in 2020 cm2 field, TLDs were calibrated at first. Gamma calibration was performed with 10 and 18 MV linac and neutron calibration was done with 241Am-Be neutron source. For simulation, MCNPX code was used then calculated neutron dose equivalent was compared with measurement data. Neutron dose equivalent at 18 MV was measured by using TLDs on the phantom surface and depths of 1, 2, 3.3, 4, 5 and 6 cm. Neutron dose at depths of less than 3.3cm was zero and maximized at the depth of 4 cm (44.39 mSvGy-1), whereas calculation resulted  in the maximum of 2.32 mSvGy-1 at the same depth. Neutron dose at 10 MV was measured by using TLDs on the phantom surface and depths of 1, 2, 2.5, 3.3, 4 and 5 cm. No photoneutron dose was observed at depths of less than 3.3cm and the maximum was at 4cm equal to 5.44mSvGy-1, however, the calculated data showed the maximum of 0.077mSvGy-1 at the same depth. The comparison between measured photo neutron dose and calculated data along the beam axis in different depths, shows that the measurement data were much more than the calculated data, so it seems that TLD600 and TLD700 pairs are not suitable dosimeters for neutron dosimetry in linac central axis due to high photon flux, whereas MCNPX Monte Carlo techniques still remain a valuable tool for photonuclear dose studies.


Sign in / Sign up

Export Citation Format

Share Document