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Objective. A retrospective study on secondary cancer risk on carbon ion radiotherapy (CIRT) is ongoing at the Heavy Ion Medical Accelerator in Chiba (HIMAC). The reconstruction of the whole-body patient dose distribution is the key issue in the study because dose distribution only around the planning target volume was evaluated in the treatment planning system. Approach. We therefore developed a new dose reconstruction system based on the Particle and Heavy Ion Transport code System (PHITS) coupled with the treatment plan DICOM data set by extending the functionalities of RadioTherapy package based on PHITS (RT-PHITS). In the system, the geometry of patient-specific beam devices such as the range shifter, range compensator, and collimators as well as the individual patient's body are automatically reconstructed. Various functions useful for retrospective analysis on the CIRT are implemented in the system, such as those for separately deducing dose contributions from different secondary particles and their origins. Main results. The accuracy of the developed system was validated by comparing the dose distribution to the experimental data measured in a water tank and using a treatment plan on an anthropomorphic phantom. Significance. The extended RT-PHITS will be used in epidemiological studies based on clinical data from HIMAC.

Objective. A retrospective study on secondary cancer risk on carbon ion radiotherapy (CIRT) is ongoing at the Heavy Ion Medical Accelerator in Chiba (HIMAC). The reconstruction of the whole-body patient dose distribution is the key issue in the study because dose distribution only around the planning target volume was evaluated in the treatment planning system. Approach. We therefore developed a new dose reconstruction system based on the Particle and Heavy Ion Transport code System (PHITS) coupled with the treatment plan DICOM data set by extending the functionalities of RadioTherapy package based on PHITS (RT-PHITS). In the system, the geometry of patient-specific beam devices such as the range shifter, range compensator, and collimators as well as the individual patient's body are automatically reconstructed. Various functions useful for retrospective analysis on the CIRT are implemented in the system, such as those for separately deducing dose contributions from different secondary particles and their origins. Main results. The accuracy of the developed system was validated by comparing the dose distribution to the experimental data measured in a water tank and using a treatment plan on an anthropomorphic phantom. Significance. The extended RT-PHITS will be used in epidemiological studies based on clinical data from HIMAC.

Management of patient dose is an effective way to help optimize computed tomography (CT) scanning conditions and CT dose. Organ dose is one of the preferred quantities for radiation protection because of its correlation with radiation risk. To date, the WAZA-ARI dose calculator is the only freely available CT dose calculator also applicable for pediatric patients. However, no reports of its evaluation have appeared since the latest version of WAZA-ARI was released. In this study, to evaluate the latest version of WAZA-ARI, we measured the organ dose in a 5-y-old anthropomorphic phantom by a newly developed radiophotoluminescence glass dosimeter (RGD) dosimetry system and compared these results with the calculation results from WAZA-ARI. The newly designed RGDs have less angular dependence because of the additional filter. RGDs were individually calibrated with the ISOVOLT TITAN-320 x-ray generator. All the experimental measurements for this study were performed using a CT scanner. To consider the difference of CT output between the nominal and actual machine, the measured CTDIair was used to correct the calculation results obtained from WAZA-ARI. After the corrections using the measured CTDIair, the calculation results from WAZA-ARI were relatively lower than the measured results with a range of 8-20%, which corresponds to the dose difference caused by the difference in effective diameter. In conclusion, the calculation accuracy of WAZA-ARI is guaranteed when the normalization factor specific to each CT scanner (CTDIair) and the shape of the phantom are taken into consideration.

The use of carbon ion beams in cancer therapy (also known as hadron therapy) is steadily growing worldwide; therefore, the demand for more efficient dosimetry systems is also increasing because daily quality assurance (QA) measurements of hadron radiotherapy is one of the most complex and time consuming tasks. The aim of this study is to develop a two-dimensional dosimetry system that offers high spatial resolution, a large field of view, quick data response, and a linear dose–response relationship. We demonstrate the dose imaging performance of a novel digital dose imager using carbon ion beams for hadron therapy. The dose imager is based on a newly-developed gaseous detector, a well-type glass gas electron multiplier. The imager is successfully operated in a hadron therapy facility with clinical intensity beams for radiotherapy. It features a high spatial resolution of less than 1 mm and an almost linear dose–response relationship with no saturation and very low linear-energy-transfer dependence. Experimental results show that the dose imager has the potential to improve dosimetry accuracy for daily QA.

An optically read-out glass gas electron multiplier (G-GEM) detector is expected to simplify complicated quality assurance measurements for hadron therapies by imaging the dose distribution of the incident beam. However, the effect of secondary particles from the detector itself has not been well studied. In this paper, we evaluate a design that reduces the secondary particles from the cathode of a G-GEM detector. Specifically, we assembled detectors with thin cathodes and assessed their effect on the secondary particle production in simulations and experiments. The experiments were carried out under 290 MeV/u 12C ion bombardment at the Heavy Ion Medical Accelerator in Chiba. The clinical intensity of the thin cathode detector was compared with that of a conventional thick cathode G-GEM detector. The improved chamber design reduced the dose contributions of secondary particles from the cathode without degrading the dose imaging performance.

The size-specific dose estimates (SSDE) have been recommended to replace the volume computed tomography dose index (CTDIvol) because it takes patient size into account. On the other hand, organ dose is thought to be a more appropriate quantity in the radiation protection field due to its correlation with radiation risk. The web-based computed tomography (CT) dose calculator WAZA-ARIv2 only offers organ doses for adults with four different body shapes and for children with five different ages. Since the American Association of Physicists in Medicine (AAPM) offers the conversion factors for SSDE and the correlation of SSDE with organ dose has been demonstrated, implementation of the conversion table might improve the accuracy of WAZA-ARIv2. This study aimed to evaluate a body mass index (BMI)-based and age-based correction method for estimation of the organ dose by using a radiophotoluminescence dosimeter (RGD), an anthropomorphic phantom, and the dose calculator WAZA-ARIv2. RGDs were individually calibrated by using an ISOVOLT TITAN-320 x-ray generator. The ratio of the SSDE conversion factors (CFSSDE) was used as the comparison index. For the BMI-based correction method, the ratio of CFSSDE values for the adult phantoms was expected to be 1.065, and the average ratio of the organ doses for the adult phantoms was 1.163 ± 0.169. For the age-based correction method, the ratio of CFSSDE value for 5- and 10-y-old pediatric phantoms was expected to be 0.889, and the ratios of the organ doses were 0.866 ± 0.024 and 0.909 ± 0.047 for the WAZA-ARIv2 dosimetry system and RGD dosimetry system, respectively. In conclusion, both evaluations of the experimental results showed the consistency between WAZA-ARIv2 and the SSDE conversion factor table. Moreover, the importance of taking the measurement position into account when applying the mass attenuation coefficient was demonstrated according to this study.

In radiation therapy, the dose distribution is determined using a homogeneous phantom. However, given that the human body includes not only soft tissue but also air and bone, it is desirable to be able to verify the dose distribution in a human body. In the context of developing an anthropomorphic phantom dosimeter for photon therapy, there is therefore a need to improve the tissue equivalencies of Al2O3:Cr thermoluminescence dosimeters (TLDs) with a relatively high effective atomic number (11.14). For this purpose, the use of Al2O3:Cr TLDs with bulk-density control was examined by Monte Carlo simulations. Furthermore, the TL properties of several manufactured bulk-density controlled TLDs were investigated. In photon therapy, it was found that the equivalence of the bulk-density controlled TLDs relative to human body was effectively matched, while maintaining the TL characteristics of the base Al2O3:Cr TLDs.

For neutron detection applications, we have synthesised glass phosphor materials of Ce3+-doped CaO–Al2O3–B2O3 with consisting boron in two different forms of isotopes, enriched 10B and 11B, called 10B-glass and 11B-glass, respectively. For radiation detections, thermoluminescence (TL) properties of the glasses were investigated with X-ray, proton, and neutron irradiations. The TL properties of X-ray- and proton-irradiated 10B- and 11B-glasses were similar while the TL intensity of neutron-irradiated 10B-glass was much greater than that of 11B-glass. The TL of the 10B-glass was observed across the neutron fluence range of 107–1012 neutrons/cm2, and the intensity increased monotonically with neutron fluence.