Implementation of Japanese Male and Female Tomographic Phantoms to Multi-particle Monte Carlo Code for Ionizing Radiation Dosimetry

Japanese male and female tomographic phantoms, which have been developed for radio-frequency electromagnetic-field dosimetry, were implemented into multi-particle Monte Carlo transport code to evaluate realistic dose distribution in human body exposed to radiation field. Japanese tomographic phantoms, which were developed from the whole body magnetic resonance images of Japanese average adult male and female, were processed as follows to be implemented into general purpose multi-particle Monte Carlo code, MCNPX2.5. Original array size of Japanese male and female phantoms, 320x160x866 voxels and 320x160x804 voxels, respectively, were reduced into 320x160x433 voxels and 320x160x402 voxels due to the limitation of memory use in MCNPX2.5. The 3D voxel array of the phantoms were processed by using the built-in repeated structure algorithm, where the human anatomy was described by the repeated lattice of tiny cube containing the information of material composition and organ index number. Original phantom data were converted into ASCII file, which can be directly ported into the lattice card of MCNPX2.5 input deck by using in-house code. A total of 30 material compositions obtained from International Commission on Radiation Units and Measurement (ICRU) report 46 were assigned to 54 and 55 organs and tissues in the male and female phantoms, respectively, and imported into the material card of MCNPX2.5 along with the corresponding cross section data. Illustrative calculation of absorbed doses for 26 internal organs and effective dose were performed for idealized broad parallel photon and neutron beams in anterior-posterior irradiation geometry, which is typical for workers at nuclear power plant. The results were compared with the data from other Japanese and Caucasian tomographic phantom, and International Commission on Radiological Protection (ICRP) report 74. The further investigation of the difference in organ dose and effective dose among tomographic phantoms for other irradiation geometries should be carried out by employing additional tomographic phantoms to find out the dosimetric difference of Asian human phantoms from Caucasian-based phantoms.     

Dose conversion coefficients for Chinese reference adult male and female voxel phantoms from idealized neutron exposures

A whole-body voxel phantom called CRAF representing the Chinese adult female was constructed in this study from color photographs. The CRAF has a height of 160 cm and a weight of 54 kg with 80 organs and tissues, including almost all organs required in the ICRP Publication 103. Masses of all organs in CRAF are consistent with the Chinese reference data within 1%. Our research group has previously developed a Chinese reference adult male phantom called CRAM, which has a height of 170 cm and a weight of 60 kg with 80 tissues and organs. A new set of fluence-to-dose conversion coefficients based on the Chinese reference adult voxel phantoms CRAM and CRAF are presented for six idealized external neutron exposures from 10^?8 MeV to 20 MeV. The calculation of organ-absorbed doses and effective doses were performed with the Monte Carlo transport code MCNPX 2.4. The resulting dose conversion coefficients were compared with those published in ICRP Publication 116, which represents the reference Caucasian. It was observed that the two sets of organ-absorbed dose conversion coefficients agreed well for most organs in ROT and ISO geometry; however, considerable deviations were found in some organs in AP, PA, RLAT and LLAT exposures. Organ-absorbed dose coefficients difference showed good agreement with the difference of organ depth distribution between Chinese and ICRP phantoms. For neutrons with energies above 2 MeV, the effective dose conversion coefficients of Chinese reference adult are almost identical to those of ICRP Publication 116 in AP, PA, ROT and ISO geometries, while are generally 15% higher than those of ICRP Publication 116 from lateral geometries. When energies range from 10^?8 MeV to 1 MeV, differences are within 10% in AP (–5%), PA (–8%) and ROT (4%) geometries; however, relatively large discrepancies are shown in lateral and ISO geometries, with differences of 15% for LLAT, 20% for RLAT and 12% for ISO, respectively.     

Dosimetry study for a new in vivo X-ray fluorescence (XRF) bone lead measurement system

A new ¹⁰⁹Cd γ-ray induced bone lead measurement system has been developed to reduce the minimum detectable limit (MDL) of the system. The system consists of four 16 mm diameter detectors. It requires a stronger source compared to the “conventional” system. A dosimetry study has been performed to estimate the dose delivered by this system. The study was carried out by using human-equivalent phantoms. Three sets of phantoms were made to estimate the dose delivered to three age groups: 5-year old, 10-year old and adults. Three approaches have been applied to evaluate the dose: calculations, Monte Carlo (MC) simulations, and experiments. Experimental results and analytical calculations were used to validate MC simulation. The experiments were performed by placing Panasonic UD-803AS TLDs at different places in phantoms that representing different organs. Due to the difficulty of obtaining the organ dose and the whole body dose solely by experiments and traditional calculations, the equivalent dose and effective dose were calculated by MC simulations. The result showed that the doses delivered to the organs other than the targeted lower leg are negligibly small. The total effective doses to the three age groups are 8.45/9.37 μSv (female/male), 4.20 μSv, and 0.26 μSv for 5-year old, 10-year old and adult, respectively. An approval to conduct human measurements on this system has been received from the Research Ethics Board based on this research.     

不同LET碳离子对V79细胞辐射敏感性的影响

以中国仓鼠肺V79细胞为材料,利用兰州近代物理研究所重离子研究装置（HIRFL）产生的碳离子,研究了不同线性能量传递（LET）的重离子对体外培养细胞的存活效应,并与γ射线的结果作了比较。结果表明,不同LET碳离子引起细胞失活效应由大到小的顺序依次为125、200、700keV/μm。碳离子表现为无肩区的存活曲线,属单靶单击模型,γ射线表现为有肩区的存活曲线,属多靶单击模型。LET值为125、200、700keV/μm时得到的失活截面分别为35、12、8μm^2。当细胞存活比率为0.1和0.37,在LET为125keV/μm时得到相对生物学效应（RBE）值为1.47和2.19。     

TOF-PET探测器定时性能初步研究

本工作采用LYSO晶体阵列和平板型位置灵敏光电倍增管H8500对TOF-PET探测器进行了初步设计,能分辨3.2mm×3.2mm的晶体阵列。与BaF₂探测器组成时间谱仪,测量正电子湮没射线的瞬发时间谱,得到379ps的符合时间分辨率。根据已测量的BaF₂探测器时间分辨率（159ps）,可计算得到所设计的TOF-PET探测器时间分辨率为344ps。预计与此相同的两个TOF-PET探测器对正电子湮没射线的符合时间分辨率可达486ps左右,为新型PET的研究提供了有利条件。     

乳腺癌术后放疗时靶外组织剂量的研究

本文借助非均匀组织等效拟人体模型,模拟成年女性左侧乳腺癌术后放疗,研究了医用电子直线加速器产生的９ＭｅＶ电子束和６ＭＶ Ｘ射线对乳腺癌放疗时靶外组织的受照剂量。结果表明,单次照射剂量２．０Ｇｙ时,在胸壁照射区域,电子束照射时体表的受照剂量较高,位于野内左后壁的剂量明显低于野外右乳腺的剂量,野外组织受照剂量波动较大,Ｘ射线照射时野外组织受照剂量波动较小,受照剂量最高的具有一定深度的纵隔;     

Eu活化过渡法测量绝对热中子注量率

在相同条件下，以不同时间辐照Ａｕ箔和Ｅｕ箔，用γ谱仪测量＾１９８Ａｕ的４１１ｋｅＶγ射面积和＾１５２Ｅｕ的４１１ｋｅＶγ峰面积，再通过４πβ－γ符合装置测得金箔的绝对中子注量率，根据两者的峰面积之比和测得的Ａｕ箔绝对中子注量率，求得＾１５３Ｅｕ的４１１ｋｅＶγ峰面积对应的中子注量率。     

铀基体中~(237)U208keV γ射线发射率的精确测定

运用高比放射性177Lu及主要γ射线能量(208.3664keV)与237U208.000keVγ射线的高度近似性,对U样品中208keVγ射线发射率测量中的自吸收效应,进行了校正。通过测量几何的安排,使级联γ射线的合峰效应可忽略。此法可用于高原子序数物质中低能γ射线发射率的测定。     

Measurement of keV-Neutron Capture Cross Sections and Capture Gamma-Ray Spectra of 167 Er

The neutron capture cross sections and capture γ-ray spectra of ¹⁶⁷Er were measured in the neutron energy region of 10 to 90keV and at 550 keV. Using a neutron time-of-flight method with a 1.5-ns pulsed neutron source by the ⁷Li(p, n)⁷Be reaction, the measurement was performed by detecting prompt γ rays from an enriched capture sample with a large anti-Compton Nal(Tl) spectrometer. A pulse-height weighting technique was applied to observed capture γ-ray pulse-height spectra to extract capture yields. The capture cross sections were derived with the error of about 5% by using the standard capture cross sections of ¹⁹⁷Au. The present results were compared with the evaluated values of ENDF/B-VI and the previous measurement. The present measurement at 550 keV was the first one. The capture γ-ray spectra were obtained by unfolding the observed capture γ-ray pulse-height spectra. An anomalous shoulder was clearly observed around 3 MeV in the γ-ray spectra and the energy position of the shoulder was consistent with the systematics obtained in our previous work. The multiplicities of the observed γ rays were derived from the γ-ray spectra.     

Systemic study on the safety of immuno-deficient nude mice treated by atmospheric plasma-activated water

Cold atmospheric-pressure plasma is a new technology,widely used in many fields of biomedicine,especially in cancer treatment.Cold plasma can selectively kill a variety of tumor cells,and its biological safety in clinical trials is also very important.In many cases,the patient's immune level is relatively low,so we first studied the safety assessment of plasma treatment in an immunocompromised animal model.In this study,we examined the safety of immuno-deficient nude mice by oral lavage treatment of plasma-activated water,and studied the growth status,main organs and blood biochemical indexes.Acute toxicity test results showed that the maximum dose of plasma treatment for 15 rain had no lethal effect and other acute toxicity.There were no significant changes in body weight and survival status of mice after 2 rain and 4 min of plasma-activated water (PAW) treatment for 2 weeks.After treatment,the major organs,including heart,liver,spleen,lung and kidney,were not significandy changed in organ coefficient and tissue structure.Blood biochemical markers showed that blood neutrophils and mononuclear cells were slightly increased,and the others remained unchanged.Liver function,renal function,electrolytes,glucose metabolism and lipid metabolism were not affected by different doses of PAW treatment.The above results indicate that PAW treatment can be used to treat immuno-deficient nude mice without significant safety problems.     

基于数字脉冲成形技术的HPGeγ谱仪系统研究

为满足高能量分辨率γ能谱测量要求,设计了基于数字脉冲成形技术的HPGe γ谱仪系统。该系统由前端电路、数字信号处理模块和上位机软件3部分组成,实现了8192道能谱测量。本文对前端电路的设计及数字脉冲成形参数的选择进行了介绍,并用⁶⁰Co、¹³⁴Cs、¹³⁷Cs和¹⁵²Eu源对该系统进行了初步测试。测试结果表明,基于数字脉冲成形技术的HPGe γ谱仪系统对1 332 keV能量峰的能量分辨率为1.8 keV;¹⁵²Eu特征能量峰与相应道址的线性拟合参数R²=0.999 993。该系统可满足高能量分辨率γ能谱测量要求。     

利用瞬发γ射线法测量209Bi的中子非弹性散射截面

在铅铋快堆、空间堆等先进反应堆中,铋作为冷却剂和慢化剂材料被大量使用,其中子核反应截面,尤其是中子非弹性散射截面的准确性对这些核装置的安全性和经济性等具有重要的影响。基于中国原子能科学研究院HI 13串列加速器瞬发γ射线实验平台,通过瞬发γ射线法测量了209Bi在90、105和120 MeV 3个能点的中子非弹性散射截面。在相对于中子束30°、70°、110°和150°方向放置4个Clover探测器测量中子与样品相互作用产生的γ射线。实验采用相对测量,通过测量中子与48Ti发生非弹性散射发射的9835 keV γ射线的产生截面来确定209Bi的截面。209Bi金属样品的尺寸为50 mm×4 mm,参考样品为1块50 mm×1 mm的天然钛金属样品。将实验测量结果与已发表的实验数据、ENDF/B Ⅷ.0、JEFF 33、JENDL 40、ROSFOND 2010和CENDL 31等评价库数据以及Talys 195程序默认参数的计算结果进行对比,发现趋势一致,90、105 MeV能点的测量结果与Talys 195程序的计算结果符合得更好,120 MeV能点的测量结果与ROSFOND 2010评价库数据符合得更好。     

鼻咽癌放射治疗时野外组织器官剂量的研究

本文借助非均匀组织等效似人体模型，模拟鼻咽癌放射治疗，研究了＾６０Ｃｏγ射线和电子直线加速器产生的６ＭＶＸ射线对野外组织器官的受照剂量。结果表明，离照射野越近组织器官受照剂量越高，加眼晶体、垂体、甲状腺等，但睾丸的受照剂量明显高于腹部；＾６０Ｃｏγ射线照射时野外组织器官的剂量明显高于６ＭＶＸ射线；＾６０Ｃｏγ射线照射时，在耳前野野外挡铅可使眼晶体、视网膜受照剂量下降２０％，睾丸表面挡铅可使睾丸受照     

Fabrication and X-Ray Calibration of Thin Plastic Scintillator Detectors

Thin film plastic scintillator detectors were fabricated and calibrated with x rays in the 1.5-20 keV range. The calibration systems used are described. Measurements showed that the presence of a film substrate can significantly change the detector response. X-ray conversion efficiency was determined as a function of energy and shown to be a strong function of energy for low energy x rays.     

Half-life measurement of neutron-rich isotope 237Th

1 INTRODUCTIONIt has been rePorted[1l that the new neutron-rich isotoPe 237Th was produced via'"U(n,2P):"Th reaction by 14MeV/u neutron irradiations of natural uxedum and thehdelife of:3vTh has been given. Some experimental results reveal that in multi-nucleontransfer reaction (MNTR), neutron-rich projectile, neutron-rich taxget and reasonablyhigher incident energy favor the production of a heavy neutron-rich nuclei. In addition,dissiPative fragmntation of heavy taxget in the interme…     

Primary study on holdup measurement of 235U in pipe using γ-ray spectrometry and Monte Carlo simulation

The pipe holdup measurement is very important for decommissioning nuclear facilities and nuclear-material control and accounting. The absolute detection efficiencies (εsp) of full-energy γ rays peak under different source density distribution function have been simulated using the Monte Carlo (MC) software, and the counting rates (n0) of the characteristic γ rays have been measured using the γ spectrometer followed by the calculation of the holdup. The holdup is affected by the energy of γ rays, distance at which they are detected, pipe material, thickness,and source distribution of pipe, especially source distribution at a short distance. The comparative test of 235U reference materials on the inner wall of Fe and A1 pipes (the total mass of 235U is 44.6 mg and 222.8 mg, respectively) have been accomplished using this method. The determined result of 235U is 43.2mg (U0.95rel=5.4%) and 216.2mg (U0.95rel= 3.2%), respectively, which are in accordance with the reference values.     

Evaluation of Counting Efficiency of a Whole-body Counter using the EGS4 Code

Counting efficiencies of a whole-body counter installed in the Japan Atomic Energy Research Institute were evaluated using Monte Carlo simulation and measurement to validate the calculation method of the counting efficiency curves of the whole-body counter for the water-filled block-shape phantoms containing radionuclides. Consequently, the counting efficiency curves in the photon energy range of 300–1,461 keV were obtained using the Monte Carlo simulation. The calculations are in fairly good agreement with the measurements in the photon energy range of 662–1,461 keV. It was also found that the self-scattering effect of photons in the phantoms accounts for about 7% of the counting efficiency for 662 keV photons.     

闪烁薄膜探测器X/γ射线能量响应研究

为准确评估闪烁薄膜探测器(OSFD)在脉冲裂变中子参数测量中γ射线对测量结果的影响,利用Geant4程序对闪烁薄膜探测器的X（或γ）射线响应进行模拟,结合半经验电子发光效率曲线,获得探测器能量响应理论曲线,利用662 keV和1.25 MeV的单能γ射线源,以及窄谱剂量标准的48~208 keV准单能X射线能点对探测器响应进行刻度。本研究结果为闪烁薄膜探测器结构的改进,以及探测器在宽能谱脉冲X射线场测量中的应用提供了重要依据。     

CT-W_4(日立)头部扫描时患者的剂量分布

本文应用热释光剂量计和人体模型,测定了 CT-W_4(日立)全身扫描机进行了单层和20层头部扫描时患者脑组织的照射量分布、最大体表照射量、器官剂量和有效剂量当量;导出了头部扫描时患者眼晶体和甲状腺剂量的估算公式。     

Pixel X-ray detectors in epitaxial gallium arsenide withhigh-energy resolution capabilities (Fano factor experimentaldetermination)

Gallium Arsenide pixel detectors with an area of 170×320 μm² and thickness of 5 μm, realized by molecular beam epitaxy, have been designed and tested with X- and γ rays. No significant charge trapping effects have been observed, and a charge collection efficiency of 100% has been measured. At room temperature an energy resolution of 671 eV full width at half maximum (FWHM) at 59.54 keV has been obtained, with an electronic noise of 532 eV FWHM. With the detector cooled to 243 K, the electronic noise is reduced to 373 eV FWHM, and the K_α and K_β lines of the ⁵⁵Fe spectrum can be resolved. The Fano factor for GaAs has been measured at room temperature with 59.5 keV photons yielding F=0.12±0.01