Monte Carlo simulation study on the dose and dose-averaged linear energy transfer distributions in carbon ion radiotherapy

Ishikawa, Akihisa; Koba, Yusuke*; Furuta, Takuya; Chang, W.*; Yonai, Shunsuke*; Matsumoto, Shinnosuke*; Hashimoto, Shintaro; Hirai, Yuta*; Sato, Tatsuhiko

Radiological Physics and Technology, 17(2), p.553 - 560, 2024/06

https://doi.org/10.1007/s12194-024-00798-7

Development of the DICOM-based Monte Carlo dose reconstruction system for a retrospective study on the secondary cancer risk in carbon ion radiotherapy

Furuta, Takuya; Koba, Yusuke*; Hashimoto, Shintaro; Chang, W.*; Yonai, Shunsuke*; Matsumoto, Shinnosuke*; Ishikawa, Akihisa*; Sato, Tatsuhiko

Physics in Medicine & Biology, 67(14), p.145002_1 - 145002_15, 2022/07

https://doi.org/10.1088/1361-6560/ac7998

Carbon ion radiotherapy has an advantage over conventional radiotherapy such that its superior dose concentration on the tumor helps to reduce unwanted dose to surrounding normal tissues. Nevertheless, a little dose to normal tissues, which is a potential risk of secondary cancer, is still unavoidable. The Monte Carlo simulation is a good candidate for the tool to assess secondary cancer risk, including the contributions of secondary particles produced by nuclear reactions. We therefore developed a new dose reconstruction system implementing PHITS as the engine. In this system, the PHITS input is automatically created from the DICOM data sets recorded in the treatment planning. The developed system was validated by comparing to experimental dose distribution in water and treatment plan on an anthropomorphic phantom. This system will be used for retrospective studies using the patient data in National Institute for Quantum and Science and Technology.

Measurement of neutron production double-differential cross-sections on carbon bombarded with 430 MeV/nucleon carbon ions

Itashiki, Yutaro*; Imabayashi, Yoichi*; Shigyo, Nobuhiro*; Uozumi, Yusuke*; Satoh, Daiki; Kajimoto, Tsuyoshi*; Sanami, Toshiya*; Koba, Yusuke*; Matsufuji, Naruhiro*

Journal of Radiation Protection and Research, 41(4), p.344 - 349, 2016/12

https://doi.org/10.14407/jrpr.2016.41.4.344

Carbon ion therapy has achieved satisfactory results because of high curability and minimally invasiveness. However, patients have a risk to get a secondary cancer. In order to estimate the risk, it is essential to understand particle transportation and nuclear reactions in the patient's body. The particle transport Monte Carlo simulation code is a useful tool to understand them. Since the code validation for heavy ion incident reactions is not enough, the experimental data of the elementary reaction processes is needed. We measured neutron production double-differential cross-sections (DDXs) on a carbon bombarded with 430 MeV/nucleon carbon beam which is a possible candidate of future therapy beam. The experiment was performed at PH2 beam line of the HIMAC of National Institute of Radiological Sciences. The 430 MeV/nucleon carbon beam was irradiated on a 5 cm 5 cm 1 cm graphite target rotated 45 to the beam axis. The beam intensity was set to 10 particles / spill. A 0.5 mm thick NE102A plastic scintillator was placed to monitor the beam intensity. Neutrons produced in the target were measured with two sizes of NE213 liquid organic scintillators located at six angles of 15, 30, 45, 60, 75, and 90. The 5.08 cm long one was used to obtain the neutron spectra from 1 MeV to 10 MeV and the 12.7 cm long one was used above 5 MeV. The 2 mm thick NE102A plastic scintillators to discriminate charged particles were set in front of the neutron detectors. The kinetic energies of neutrons were determined by the time-of-flight (TOF) method. Background neutrons were estimated by a measurement with iron shadow bars between the target and each neutron detector. An electronic circuit for data acquisition consisted of NIM and CAMAC modules. The experimental data was compared with calculated results obtained by Monte Carlo simulation codes as PHITS. The PHITS code reproduced the experimental data well.

Measurement of neutron production cross sections from heavy ion induced reaction

Shigyo, Nobuhiro*; Uozumi, Yusuke*; Imabayashi, Yoichi*; Itashiki, Yutaro*; Satoh, Daiki; Kajimoto, Tsuyoshi*; Sanami, Toshiya*; Koba, Yusuke*; Takada, Masashi*; Matsufuji, Naruhiro*; et al.

JAEA-Conf 2014-002, p.81 - 87, 2015/02

https://doi.org/10.11484/jaea-conf-2014-002

Cancer therapy using heavy ion beam has been adopted as highly advanced medical treatment by reason of its clinical advantages. It has become more important to estimate the risk of secondary cancer from recent survey. During treatment, secondary particles such as neutrons and -rays are producedby heavy ion induced nuclear reactions in a patient body as well as beam delivery apparatuses. For the risk assessment of secondary cancer, it is essential to know contribution of secondary neutrons by extra dose to organs in the vicinity of the irradiated tumor because the secondary neutron has a long flight path length and gives undesired dose to normal tissues in a wide volume. The experimental data of neutron energy spectra are required for dose estimations with high accuracy. Especially, precise data around neutron energy of 1 MeV is required because neutron of the energy region has a large relative biological eectiveness. Estimation of the secondary neutron yield data is important for estimation of radiation safety on both of workers and public in treatment facilities.

Measurement of 100- and 290-MeV/A carbon incident neutron production cross sections for carbon, nitrogen and oxygen

Shigyo, Nobuhiro*; Uozumi, Yusuke*; Uehara, Haruhiko*; Nishizawa, Tomoya*; Mizuno, Takafumi*; Takamiya, Masanori*; Hashiguchi, Taro*; Satoh, Daiki; Sanami, Toshiya*; Koba, Yusuke*; et al.

Nuclear Data Sheets, 119, p.303 - 306, 2014/05

https://doi.org/10.1016/j.nds.2014.08.083

Heavy ion cancer therapy has been increased by reason of its clinical advantages. During the treatment, the secondary particles such as neutron and -ray are produced by nuclear reactions of a heavy ion incidence on a nucleus in a patient body. Estimation of the secondary neutrons yields data is essential for assessment of radiation safety on both of workers and public in treatment facilities. We have measured the neutron yields from carbon ion incidence on carbon, nitrogen and oxygen targets in wide angular range from 15 to 90 with 100- and 290-MeV/u.

Measurement of 100 MeV/u carbon incident neutron production cross sections on a carbon target

Shigyo, Nobuhiro*; Uozumi, Yusuke*; Uehara, Haruhiko*; Nishizawa, Tomoya*; Mizuno, Takafumi*; Satoh, Daiki; Sanami, Toshiya*; Koba, Yusuke*; Takada, Masashi*; Matsufuji, Naruhiro*

JAEA-Conf 2013-002, p.137 - 142, 2013/10

https://doi.org/10.11484/jaea-conf-2013-002

Heavy ion cancer therapy has been increased by reason of its clinical advantages. During the treatment, the secondary particles such as neutron and -ray are produced by nuclear reactions of a heavy ion incidence on a nucleus in a patient body. Estimation of double differential cross sections of secondary neutron is important to risk assessment of extra dose to organs in the vicinity of the irradiated tumor. Accurate data in neutron energy around 1 MeV is required because neutron in the energy region has large relative biological effectiveness. Neutron double differential cross sections by inducing 290 MeV/u carbon ion to bio-elements have been obtained experimentally. In order to have knowledge of neutron production by deceleration carbon in a human body, we measured the neutron yields from carbon ion incidence on a carbon target of neutron energy below 1 MeV in wide angular range from 15 to 90 with 100 MeV/u.

Measurements of neutron- and photon-production cross sections from heavy-ion reactions on tissue equivalent elements

Uozumi, Yusuke*; Shigyo, Nobuhiro*; Kajimoto, Tsuyoshi*; Hirabayashi, Keiichi*; Uehara, Haruhiko*; Nishizawa, Tomoya*; Satoh, Daiki; Sanami, Toshiya*; Koba, Yusuke*; Takada, Masashi*; et al.

HIMAC-138, p.237 - 238, 2012/08

In the heavy-ion radiotherapy, considerable discussion has been attracted regarding the potential for second cancer induction by secondary neutrons produced from the primary heavy-ion fragmentation. It is important to measure energy-angle double-differential cross sections (DDXs) of neutron- and photon-productions in heavy-ion nuclear reactions. Since it is notoriously hard to measure the spectral cross sections of neutrons in an energy range of around 1 MeV where the RBE value reaches at its maximum. In the project by last year, experiments were carried out at the synchrotron HIMAC of NIRS, Japan. The beams were C and O of 290 MeV/u and bombarded a carbon target. In measurements of neutrons and photons were used liquid scintillator detectors of 5" and 2". We have succeeded to lower the neutron energy threshold down to 0.6 MeV. The present results for neutron productions are in reasonable agreements with PHITS. Since our goal in technical aspects has been fulfilled, measurements will be continued for other reactions.

Neutron-production double-differential cross sections from heavy-ion interactions

Satoh, Daiki; Moriguchi, Daisuke*; Kajimoto, Tsuyoshi*; Koba, Yusuke*; Nakamura, Yasuhiro*; Shigyo, Nobuhiro*; Ueyama, Masahiko*; Uozumi, Yusuke*; Yoshioka, Masakatsu*; Matsufuji, Naruhiro*; et al.

Journal of the Korean Physical Society, 59(2), p.1741 - 1744, 2011/08

https://doi.org/10.3938/jkps.59.1741

The data of neutron production from heavy-ion interactions are of great importance for the dose assessment in heavy-ion therapy. We have already evaluated the data of neutron production for thick targets, in which the incident heavy ions completely stop, by the measurements and the reevaluation of the existing data reported by Kurosawa et al. As a next step of the research, we plan to evaluate the neutron-production cross-section data for thin targets. These data are useful to understand the mechanism of heavy-ion interaction, and improve the reaction model in particle transport codes. The previously reported cross-section data by Iwata et al. were revised by using a new set of neutron-detection efficiency values calculated with SCINFUL-QMD code. While the original data gave the larger values than the predictions of particle transport codes above 200 MeV due to the underestimation of the efficiencies, it was improved by this revision. In addition, we have started the new cross-section measurements at HIMAC. All the data of neutron-production cross sections were compared with the predictions of particle transport codes.

Study of neutron and photon production cross sections for second cancer risk assessment in heavy-ion therapy

Uozumi, Yusuke*; Iwamoto, Hiroki*; Koba, Yusuke*; Matsufuji, Naruhiro*; Sanami, Toshiya*; Satoh, Daiki; Shigyo, Nobuhiro*; Takada, Masashi*; Ueyama, Masahiko*; Yoshioka, Masakatsu*; et al.

Progress in Nuclear Science and Technology (Internet), 1, p.114 - 117, 2011/02

https://doi.org/10.15669/pnst.1.114

It is important to assess and suppress the potential for second cancer induction by secondary neutrons produced in primary heavy-ion fragmentation in patient body. Since it is very difficult to measure high-energy neutron doses in mixed radiation fields, a Monte-Carlo simulation approach has attracted much attention as an alternative for neutron dose estimation. It is notoriously hard to reproduce the spectral cross sections of neutrons from high-energy heavy-ion collisions. We, therefore, have planned experiments to measure energy-angle double-differential cross sections of nuclear reactions.

Constructing Monte Carlo calculation phase space files for retrospective dose analysis of heavy ion radiotherapy

Hirai, Yuta*; Koba, Yusuke*; Yonai, Shunsuke*; Chang, W.*; Ishikawa, Akihisa; Shinsho, Kiyomitsu*

no journal, , 

no abstracts in English