Diyun Shu

GEANT4 calculations of neutron dose in radiation protection using a homogeneous phantom and a Chinese hybrid male phantom

The purpose of this study is to verify the feasibility of applying GEANT4 (version 10.01) in neutron dose calculations in radiation protection by comparing the calculation results with MCNP5. The depth dose distributions are investigated in a homogeneous phantom, and the fluence-to-dose conversion coefficients are calculated for different organs in the Chinese hybrid male phantom for neutrons with energy ranging from 1 × 10(-9) to 10 MeV. By comparing the simulation results between GEANT4 and MCNP5, it is shown that using the high-precision (HP) neutron physics list, GEANT4 produces the closest simulation results to MCNP5. However, differences could be observed when the neutron energy is lower than 1 × 10(-6) MeV. Activating the thermal scattering with an S matrix correction in GEANT4 with HP and MCNP5 in thermal energy range can reduce the difference between these two codes.

Monte Carlo study of the beam shaping assembly optimization for providing high epithermal neutron flux for BNCT based on D–T neutron generator

In this study, a beam shaping assembly with high epithermal neutron flux output was designed based on a D–T neutron generator using Monte Carlo N-particle Transport Code. D2O-54Fe and AlF3-60Ni interlayer moderator, efficient multiplier, filters, and reflector were used to improve the neutron beam quality according to the requirements of boron neutron capture therapy while maintaining high flux of epithermal neutron beam. In addition, the dose performance of the beam from our proposed facility was assessed in the Snyder head phantom. The simulation results proved that the proposed neutron beam was applicable to the treatment of deep-seated brain tumor.

Determination of the relationship between dose deposition and Cerenkov photons in homogeneous and heterogeneous phantoms during radiotherapy using Monte Carlo method

To explore the response relationship between Cerenkov photons and dose deposition, which is the theoretical premise of dose measurement based on Cerenkov effect, Geant4 was used to simulate the process of homogeneous and heterogeneous phantoms irradiated with monoenergetic or clinical beam energy spectrum. Results showed certain response relationship between Cerenkov photons and dose deposition regardless of the phantom used under different irradiation conditions. However, deviation observed in the axial distribution of dose deposition as characterized by Cerenkov photons was larger under electron beam than under photon beam.

A Monte Carlo-based radiation safety assessment for astronauts in an environment with confined magnetic field shielding

The active shielding technique has great potential for radiation protection in space exploration because it has the advantage of a significant mass saving compared with the passive shielding technique. This paper demonstrates a Monte Carlo-based approach to evaluating the shielding effectiveness of the active shielding technique using confined magnetic fields (CMFs). The International Commission on Radiological Protection reference anthropomorphic phantom, as well as the toroidal CMF, was modeled using the Monte Carlo toolkit Geant4. The penetrating primary particle fluence, organ-specific dose equivalent, and male effective dose were calculated for particles in galactic cosmic radiation (GCR) and solar particle events (SPEs). Results show that the SPE protons can be easily shielded against, even almost completely deflected, by the toroidal magnetic field. GCR particles can also be more effectively shielded against by increasing the magnetic field strength. Our results also show that the introduction of a structural Al wall in the CMF did not provide additional shielding for GCR; in fact it can weaken the total shielding effect of the CMF. This study demonstrated the feasibility of accurately determining the radiation field inside the environment and evaluating the organ dose equivalents for astronauts under active shielding using the CMF.

Influence of Neutron Sources and 10B Concentration on Boron Neutron Capture Therapy for Shallow and Deeper Non-small Cell Lung Cancer.

Abstract Boron Neutron Capture Therapy (BNCT) is a radiotherapy that combines biological targeting and high Linear Energy Transfer (LET). It is considered a potential therapeutic approach for non-small cell lung cancer (NSCLC). It could avoid the inaccurate treatment caused by the lung motion during radiotherapy, because the dose deposition mainly depends on the boron localization and neutron source. Thus, 10B concentration and neutron sources are both principal factors of BNCT, and they play significant roles in the curative effect of BNCT for different cases. The purpose was to explore the feasibility of BNCT treatment for NSCLC with either of two neutron sources (the epithermal reactor at the Massachusetts Institute of Technology named “MIT source” and the accelerator neutron source designed in Argentina named “MEC source”) and various boron concentrations. Shallow and deeper lung tumors were defined in the Chinese hybrid radiation phantom, and the Monte Carlo method was used to calculate the dose to tumors and healthy organs. The MEC source was more appropriate to treat the shallow tumor (depth of 6 cm) with a shorter treatment time. However, the MIT source was more suitable for deep lung tumor (depth of 9 cm) treatment, as the MEC source is more likely to exceed the skin dose limit. Thus, a neutron source consisting of more fast neutrons is not necessarily suitable for deep treatment of lung tumors. Theoretical distribution of 10B in tumors and organs at risk (especially skin) was obtained to meet the treatable requirement of BNCT, which may provide the references to identify the feasibility of BNCT for the treatment of lung cancer using these two neutron sources in future clinical applications.

Optimization of the Compton camera for measuring prompt gamma rays in boron neutron capture therapy

Optimization of the Compton camera for measuring prompt gamma rays (0.478MeV) emitted during boron neutron capture therapy (BNCT) was performed with Geant4. The parameters of the Compton camera were determined as follows: 3cm thick - 10cm wide scatter detector (Silicon), 10cm thick - 10cm wide absorber detector (Germanium), and 1cm distance between the scatter and absorber detectors. For a typical brain tumor treatment, the overall detection efficiency of the optimized Compton camera was approximately 0.1425% using the Snyders head phantom with a sphere tumor (4cm diameter and ~1cm depth).

Calculations of S values and effective dose for the radioiodine carrier and surrounding individuals based on Chinese hybrid reference phantoms using the Monte Carlo technique.

The S values for the thyroid as the radioiodine source organ to other target organs were investigated using Chinese hybrid reference phantoms and the Monte Carlo code MCNP5. Two radioiodine isotopes (125)I and (131)I uniformly distributed in the thyroid were investigated separately. We compared our S values for (131)I in Chinese phantoms with previous studies using other types of phantoms: Oak Ridge National Laboratory (ORNL) stylized phantoms, International Commission on Radiological Protection (ICRP) voxel phantoms, and University of Florida (UF) phantoms. Our results are much closer to the UF phantoms. For each specific target organ, the S value for (131)I is larger than for (125)I in both male and female phantoms. In addition, the S values and effective dose to surrounding face-to-face exposed individuals, including different genders and ages (10- and 15-year-old juniors, and adults) from an adult male radioiodine carrier were also investigated. The target organ S values and effective dose for surrounding individuals obey the inverse square law with the distance between source and target phantoms. The obtained effective dose data in Chinese phantoms are comparable to the results in a previous study using the UF phantoms. The data generated in this study can serve as the reference to make recommendations for radiation protection of the Chinese patients or nuclear workers.

Analysis on the emission and potential application of Cherenkov radiation in boron neutron capture therapy: A Monte Carlo simulation study

This paper was aimed to explore the physics of Cherenkov radiation and its potential application in boron neutron capture therapy (BNCT). The Monte Carlo toolkit Geant4 was used to simulate the interaction between the epithermal neutron beam and the phantom containing boron-10. Results showed that Cherenkov photons can only be generated from secondary charged particles of gamma rays in BNCT, in which the 2.223 MeV prompt gamma rays are the main contributor. The number of Cherenkov photons per unit mass generated in the measurement region decreases linearly with the increase of boron concentration in both water and tissue phantom. The work presented the fundamental basis for applications of Cherenkov radiation in BNCT.

Modulation of lateral positions of Bragg peaks via magnetic fields inside cancer patients: Toward magnetic field modulated proton therapy

Purpose: This work investigated whether the Bragg peak (BP) positions of proton beams can be modulated to produce uniform doses and cover a tumor under the magnetic fields inside cancer patients, and whether magnetic field modulated proton therapy (MMPT) is effective in vital organ protection. Methods: The authors initially constructed an ideal water phantom comprising a central tumor surrounded by cuboid organ regions using GEANT4. Second, we designed the proton beams passing through the gap between two adjacent organ regions during beam configuration. Third, we simulated the beam transports under magnetic fields inside the phantom through GEANT4. Then, the beams were discarded, which did not stop in the tumor. Fourth, the authors modulated the intensities of the remaining beams to produce uniform tumor doses. Subsequently, the calculated MMPT doses were compared with those of traditional methods, such as single, opposing, orthogonal, and box fields. Moreover, the authors repeated the above research procedures for abdominal anatomies comprising tumors at the pancreatic tail and liver to evaluate whether MMPT is effective for the human anatomy. Results: For the water phantom, the vital organ doses were approximately 50%, 30%, 30%, and 15% for the single, opposing, orthogonal, and box fields, respectively. As the vital organ doses decreased, the organ volume receiving proton irradiations for the opposing, orthogonal, and box fields increased by two, two, and four times compared with that for the single field. The vital organ volume receiving proton irradiations were controlled to a fairly low level through MMPT, whereas the BP positions of the proton beams were properly modulated through the magnetic fields inside the phantom. The tumor was sufficiently covered by a 95% dose line, and the maximum tumor doses were smaller than 110%. For the pancreatic tumor case, the proton beams were curved and bypassed the kidney to generate uniform doses inside the tumor through MMPT. In the liver tumor case, the liver volume receiving proton irradiations was reduced by approximately 40% through MMPT compared with traditional methods. Conclusions: The BP positions can be intentionally modulated to produce uniform tumor doses under the magnetic fields inside cancer patients. In some special cases, the vital organs surrounding the tumor can almost be exempted from proton irradiations without sacrificing tumor dose coverage through MMPT. For the tumors inside parallel organs, the parallel organ volume receiving proton irradiations was largely reduced through MMPT. The results of this study can serve as beneficial implications for future proton therapy studies with reduced vital organ damage and complications.

Measurement of dose in radionuclide therapy by using Cerenkov radiation

This work aims to determine the relationship between Cerenkov photon emission and radiation dose from internal radionuclide irradiation. Water and thyroid phantoms were used to simulate the distribution of Cerenkov photon emission and dose deposition through Monte Carlo method. The relationship between Cerenkov photon emission and dose deposition was quantitatively analyzed. A neck phantom was also used to verify Cerenkov photon detection for thyroid radionuclide therapy. Results show that Cerenkov photon emission and dose deposition exhibit the same distribution pattern in water phantom, and this relative distribution relationship also existed in the thyroid phantom. Moreover, Cerenkov photon emission exhibits a specific quantitative relation to dose deposition. For thyroid radionuclide therapy, only a part of Cerenkov photon produced by thyroid could penetrate the body for detection; therefore, the use of Cerenkov radiation for measurement of radionuclide therapy dose may be more suitable for superficial tumors. This study demonstrated that Cerenkov radiation has the potential to be used for measuring radiation dose for radionuclide therapy.