同步辐射X射线自由空气电离室电子损失和散射荧光修正因子的蒙卡模拟

采用了蒙特卡罗程序EGS5对6~20keV同步辐射低能X射线自由空气电离室的电子损失修正因子和散射荧光修正因子进行模拟计算。结果表明,对于能量范围6~20keV的低能X射线,电子损失修正因子的影响可忽略不计;而当能量增加时,荧光散射修正因子数值逐渐增加。     

Mo靶X射线空气比释动能及校准因子测量

使用低能X射线自由空气基准电离室对乳腺Mo靶X射线场的空气比释动能进行量值复现,利用绝对测量方法测得电离电流值,结合相关修正因子计算得到该辐射场中600 mm处四个辐射质的空气比释动能值;在同一点处使用传递电离室RC6M进行测量,得到该电离室的刻度因子,与BIPM所测得的刻度因子相差最大为0.13%,在不确定度范围内相符。     

抽真空法测量自由空气电离室空气衰减修正因子

空气衰减对自由空气电离室是最大的修正项,对总的修正因子不确定度影响也大。本文采用钼靶X射线、真空管测试系统和圆柱型自由空气电离室测量电离电流,用EGSnrc(Electron Gamma Shower)程序模拟恒压管对X射线束额外损失的影响;用抽真空法对圆柱型自由空气电离室空气衰减修正因子的测量,修正了实际测量中圆柱型自由空气电离室限束光阑入射面到收集极这段距离的空气衰减,得到准确的电离电流测量值。结果表明:自由空气电离室的电离电流与恒压管的压强成正比,恒压管对于X射线束额外损失小于0.5%;在钼靶X射线基准的4个辐射质条件下测得的圆柱型自由空气电离室空气衰减修正因子与德国物理技术研究院(The Physikalisch-Technische Bundesanstalt,PTB)的测量结果比较,呈现相同的变化趋势,符合实验要求和国际标准。圆柱型自由空气电离室空气衰减修正因子的实验测量对于钼靶X射线空气比释动能的绝对测量具有科学参考价值。     

乳腺X射线空气比释动能标准装置的研究

基于医用乳腺X射线诊断机,设计建造了乳腺X射线参考辐射装置。通过拟合法测得各辐射质下的半值层,实验结果表明辐射质达到既定要求。利用溯源至低能X射线空气比释动能基准的RC6M作为标准电离室,得到了乳腺X射线参考辐射场的空气比释动能率,实现了乳腺X射线半导体剂量仪的校准。     

低能X射线水吸收剂量测量的散射辐射研究

低能X射线常应用于浅层放射治疗,其空气比释动能或水吸收剂量通常采用平板电离室进行测量。为了更好地了解平板电离室在低能X射线校准过程中的响应情况,以及随辐射野变化所引起的散射情况,在低能X射线标准辐射场中,对4个参考辐射质（30 kV、25 kV、50 kV(b)和50 kV(a)）进行了蒙特卡罗模拟,同时对两种常用的PTW23344和PTW23342电离室分别在空气中和模体中进行了校准测量,并改变辐射野大小。结果表明：两种电离室的读数随着辐射野直径增大而增加,但总体趋势逐渐平缓。两种电离室空气读数和模体读数之比随着辐射野直径减小而减少,总体趋势也逐渐平缓。PTW23344电离室在辐射野4.5～9 cm范围的水吸收剂量刻度因子平均增幅是辐射野9～13.5 cm范围的水吸收剂量刻度因子平均增幅的2.85倍;PTW23342电离室在辐射野2.03～4.05 cm范围的水吸收剂量刻度因子平均增幅是辐射野4.05～6.08 cm范围的水吸收剂量刻度因子的平均增幅的1.50倍。低能X射线水吸收剂量测量,要使辐射野完全覆盖电离室灵敏体积,以达到电子平衡测量条件,又不能过大导致过多散射造成伤害。     

250~600 kV X射线空气比释动能量值复现方法研究

本文依托250~600 kV X射线光机,建立高能量段的重过滤窄谱X射线辐射质,研制石墨空腔电离室,通过蒙特卡罗模拟和实验测量完成250~600 kV X射线空气比释动能量值复现。在300 kV辐射质下,利用自由空气电离室和石墨空腔电离室完成X射线空气比释动能量值复现,相对标准不确定度分别为0.61%和0.45%,两种方法测量结果相对偏差为0.09%。利用研制的石墨空腔电离室在¹³⁷Cs和⁶⁰Co γ射线基准辐射场中完成空气比释动能的量值复现,结果与基准值的相对偏差分别为0.27%和0.39%,在不确定度范围内等效一致,验证了石墨空腔电离室测量250~600 kV X射线空气比释动能方法的可行性。     

涂硼电离室的X、γ射线响应特性研究

通过实验研究了X和γ射线空气比释动能率、能量对涂硼电离室的线性、X和γ感应度和补偿特性的影响,研究结果表明:涂硼电离室随X和γ射线空气比释动能率变化在一定范围内保持线性,涂硼电离室的X和γ感应度不仅与射线能量有关,还与射线空气比释动能率有关;涂硼补偿电离室的最佳补偿电压需通过工程实践加以确定。     

14MeV中子吸收剂量测量

本文叙述了用双探测器技术测定(n,r)混合场中子和光子剂量分量的方法。在窄束~(60)Coγ辐射场中对电离室进行了γ刻度并给出结果。计算了组织等效电离室的k_T值。用铅减弱法测定了碳电离室、铝电离室和GM-2计数管的k_U值。在T(d,n)~He中子场中实验测定了各项修正因子,最后给出了自由空气中生物组织的中子和光子比释动能分量的测量结果以及总不确定度。     

同步辐射低能X射线的照射量测量与剂量计算

用自制自由空气电离室，在能量为２－１２ｋｅＶ同步辐射光束线现场测量了单能Ｘ射线的电离量，依据Ｘ射线在空气中的传输和衰减特性及能量转移系数，计算了电离室入射口的照射剂量值。进而求出在空气中的相应比释动能和光子通量。讨论了软Ｘ射线照射量随能量的分布特性及混合能量Ｘ射线的照射量测量方法。     

胶片扫描法对低能X射线标准辐射场的研究

采用胶片剂量计测量了低能X射线辐射装置距X射线光管焦斑不同距离辐射野的大小,得出在距离光管焦斑1 000 mm的参考面辐射野大小及均匀性,并与二维矩阵电离室扫描结果进行了对比。实验结果表明,在距X射线光源焦斑1 000 mm处,在保证直径为100 mm的均匀野的条件下,非均匀性不大于1.5%。在保证非均匀性不大于5%和50%条件下,均匀野大小分别为130 mm和145 mm,满足了低能X射线空气比释动能基准装置量值复现,国际比对和向下量值传递的要求。     

Measurement of Number Albedo of Backscattered Photons for Tin and Lead

A computer code, which calculates the transients of heat flux from simulated nuclear fuel rods by using the transients of rod surface temperature and the heat conduction equation in the rod, was developed in order to investigate the heat transfer modes throughout the reflood phase in PWR-LOCA experiments. The code was applied to the Slab Core Reflood Tests which are part of the Large Scale Reflood Test Program at the Japan Atomic Energy Research Institute. For defining the heat transfer modes during reflood, it is important to obtain accurate heat flux from rod under a wide rod temperature change ranging higher than 1,300 to 300 K and a rapid rod temperature change due to quench, which are principal features in heat transfer during reflood phase. Therefore, the effects of both temperature dependency on physical properties of rod and the axial heat conduction along rod on the heat flux calculation were first investigated. As the results, it was made clear that the temperature dependency on the physical properties should be taken into account and that the effect of axial heat conduction along the rod was negligible except in a very short length of rod at the quench front. The results calculated by the code for the Slab Core Tests when compared with the existing correlations could define the heat transfer modes clearly all through the reflood phase but the recommendations for further investigations were suggested.     

Dose Conversion Coefficients for External Photons Based on ICRP 1990 Recommendations

Monte Carlo calculations were performed to estimate the effective doses E for external photons based on the recent proposals in the ICRP 1990 Recommendations. Twelve photon energies between 17 keV and 8.5 MeV and eleven irradiation geometries were selected to be applicable to many exposure conditions encountered in the working and living environment. A MIRD-based unisex phantom was used in conjunction with the Monte Carlo transport code MORSE-CG. The results were presented as a form of dose conversion coefficients transforming the air kerma or fluence in free air to the effective dose. These coefficients were given in graphical and tabular forms. Analyses of organs' fractional contribution to E showed that the gonadal exposure has generally a great contribution for all the geometries except the incidence from above. A comparison of conversion coefficients with other results gave a reasonably satisfactory agreement. Finally, the ambient dose equivalent H ^*(10), one of the operational quantities proposed by the ICRU, was found to give conservative estimates of E for most of the irradiation geometries considered, but it gives a considerable overestimate of E at the incidences from above and below.     

Calculations of Effective Dose and Ambient Dose Equivalent Conversion Coefficients for High Energy Photons

The conversion coefficients from photon fluence to ambient dose equivalent, H* (10) and effective doses were calculated for photons up to 10 GeV. A Monte Carlo code EGS4 was used for these calculations and secondary particle transports were considered. The calculated ambient dose equivalents were compared to the calculated effective doses. The comparison shows that the ambient dose equivalents at 1 cm depth, H* (10) underestimate the effective doses at the energy above 5MeV. H* (10) is not suitable operational quantity since it does not provide reasonable estimation of effective dose. It is difficult to define the operational quantity which can be consistently used for photons from low energy to high energy above 10 MeV. Instead of operational quantities, the maximum effective dose in various irradiation geometries can be used for shielding design calculations.     

A Monte Carlo Model for Gamma-Ray Klein-Nishina Scattering Probabilities to Finite Detectors

This report introduces the Monte Carlo simulating processes for gamma-ray Klein-Nishina scattering probabilities to finite detectors and a few modifications for producing photon mode and gamma production data from the neutron collision. Those approaches have been used in MCNP code. The calculation results are given according to the primary continuous photons, the line photons and the Compton photons, respectively. The results are compared with that of MCNP code. It indicates that the approach is valid and efficient for deep-penetration problems.     

大面积塑料闪烁体中荧光光子收集研究

利用Geant－3软件包建立了一套计算塑料闪烁体中可见光产生和收集的程序，并与实验进行了对比，二者基本一致。     

Imaging with Photons: A Unified Picture Evolves

The square root of the density of exposure quanta at the image plane is a popular measure of image quality for photon images. This is in fact only an upper limit which is rarely realized in the image. It is the density of noise equivalent quanta (NEQ) deduced from image measurements which is relevant to real imagery. In general NEQ is a non-trivial function of spatial frequency. Examples are taken from screen/ film mammography, electrostatic mammography, and computed tomography. The signal-to-noise ratios computed from these NEQ values characterize the performance of an ideal observer confronted with the image and a detection task. This sets goals for real observer performance, i. e., image processing and display for human acquisition.     

Position Determination of High Energy Photons in Lead Glass

Two 25 element SF5 lead glass Cerenkov counter arrays have been used in the study of photon and ?° production in pN collisions at Fermilab. The method used to identify shower patterns, and the determination of the position of the photon in the lead glass arrays in the energy range 2-32 GeV is presented. The method enables the spatial position of photons in this energy range width to be measured with a resolution of ? = 0.25 inches.     

Phosphors’ lifetime measurement employing the Time Between Photons method

The Time Between Photons theory (hereafter TBP) is applied to the evaluation of the lifetime of phosphors employed in the Ion Photon Emission Microscope (IPEM). IPEM allows Radiation Effects Microscopy (REM) without focused ion beams and appears to be the best tool for the radiation hardness assessment of modern integrated circuit at cyclotron energies. IPEM determines the impact point of a single ion onto the sample by measuring the light spot produced on a thin phosphor layer placed on the sample surface. The spot is imaged by an optical microscope and projected at high magnification onto a Position Sensitive Detector (PSD). Phosphors, when excited by an ion, emit photons with a particular lifetime, which is important to evaluate. We measured the statistical distribution of the Time Between consecutive detected Photons (TBP) for several phosphors and have been able to link it to their lifetime employing a theory that is derived in this paper. The single-photon signals are provided by the IPEM-PSD, or faster photomultipliers when high-speed materials had to be assessed.