Calibration of a neutron dose rate meter in various neutron standard fields

This paper presents the calibration of a neutron dose rate meter and the evaluation of its calibration factors(CFs)in several neutron standard fields(i.e.,two standard fields with bare sources of252Cf and241Am-Be,and five simulated workplace fields with241Am-Be moderated sources).The calibration in standard fields with bare sources was conducted by following the recommendations of the ISO 8529 standard.The measured total neutron ambient dose equivalent rates,denoted as H*(10)tot,were analyzed to obtain direct components,denoted as H*(10)dir,using a reduced fitting method.The CF was then calculated as the ratio between the conventional true value of the neutron ambient dose equivalent rate in a free field,denoted as H*(10)FF,and the value of H*(10)dir.In contrast,in the simulated workplace neutron fields,the calibration of the neutron dose rate meter was conducted by following the ISO 12789 standard.The CF was calculated as the ratio between the values of H*(10)totmeasured by a standard instrument(i.e.,Bonner sphere spectrometer)and the neutron dose rate meter.The CF values were obtained in the range of 0.88–1.0.The standard uncertainties(k=1)of the CFs were determined to be in the range of approximately 6.6–13.1%.

Neutron dose measurement in carbon ion radiation therapy at HIRFL(IMP)

For radiation protection purposes, the neutron dose in carbon ion radiation therapy at the HIRFL （Heavy Ion Research Facility in Lanzhou） was investigated. The neutron dose from primary ^12C ions with a specific energy of 100 MeV/u delivered from SSC was roughly measured with a standard Anderson-Broun rem-meter using a polyethylene target at various distances. The result shows that a maximum neutron dose contribution of 19 mSv in a typically surface tumor treatment was obtained, which is less than 1% of the planed heavy ion dose and is in reasonable agreement with other reports. Also the T-ray dose was measured in this experiment using a thermo luminescent detector.

Study of neutron dose equivalent at the HIRFL deep tumor therapy terminal

The secondary neutron fields at the deep tumor therapy terminal at HIRFL（Heavy Ion Research Facility in Lanzhou） were investigated. The distributions of neutron ambient dose equivalent were measured with a FHT762Wendi-II neutron ambient dose equivalent meter as ^（12）C ions with energies of 165, 207, 270, and 350 Me V/u were bombarded on thick tissue-like targets. The thickness of targets used in the experiments was larger than the range of the carbon ions. The neutron spectra and dose equivalent were simulated by using FLUKA code, and the results agree well with the experimental data. The experiment results showed that the neutron dose produced by fragmentation reactions in tissue can be neglected in carbon-ion therapy, even considering their enhanced biological effectiveness.These results are also valuable for radiation protection, especially in the shielding design of high energy heavy ion medical machines.

Fast neutron radiation inactivation of Bacillus subtilis:Absorbed dose determination

In this paper,fast neutron inactivation effects of Bacillus subtilis were investigated with fission fast neutrons from CFBR-Ⅱreactor of INPC(Institute of Nuclear Physics and Chemistry)and mono-energetic neutrons from the Van de Graaff accelerator at Peking University.The method for determining the absorbed dose in the Bacillus subtilis suspension contained in test tubes is introduced.The absorbed dose,on account of its dependence on the volume and the form of confined state,was determined by combined experiments and Monte Carlo method.Using the calculation results of absorbed dose,the fast neutron inactivation effects on Bacillus subtilis were studied.The survival rates and absorbed dose curve was constructed.

Energy spectrum measurement and dose rate estimation of natural neutrons in Tibet region

In this work, natural neutron spectra at nine sites in Tibet region were measured using a multi-sphere neutron spectrometer. The altitude-dependence of the spectra total fluence rate and ambient dose equivalent rate were analyzed. From the normalized natural neutron spectra at different altitudes, the spectrum fractions for neutrons of greater than 0.1 MeV do not differ obviously, while those of the thermal neutrons differ greatly from each other. The total fluence rate, effective dose rate and the ambient dose equivalent rate varied with the altitude according to an exponential law.

Simulation study of the dose and energy responses of FNTD personal neutron dosimetry

The objective of this work was to use the Geant4 toolkit to perform simulation studies on the personal dose response of fluorescent nuclear track detectors(FNTDs).The entire structure of the FNTD response can be designed,and the detector's energy and dose responses can be optimized in a broad energy range(0.01 eV-20 MeV). In general, the detectors used ~6LiF and CH_2 converters that have high energy and high dose response at neutron energies lower than 10 eV and greater than 1 MeV, respectively. The method of least squares was used to optimize the dose response of H*(10) and the energy response corresponding to Rtotal. The values of the optimized response of H*(10) lie between 0.8 and 1.4, corresponding to the energy ranges 0.01 eV-70 keV and 4-14 MeV, respectively. This occupies nearly eight out of the nine orders of the total energy range. Even though the optimized response of Rtotal is constrained between 0.89 and 1.1 in the energy range of 0.01 eV-20 MeV, it is suitable for obtaining the broad neutron spectrum of fluence with good accuracy.

SiC探测器的中子和γ性能测试

第三代SiC半导体探测器具有体积小、响应时间快、中子/伽马(n/γ)甄别容易等优点,广泛应用于反应堆堆芯剂量监测。本文针对自研的第三代SiC半导体探测器,采用电子束蒸发真空镀膜的技术将中子转换层材料^(6)LiF(^(6)Li丰度为95%)喷镀到SiC基底上,厚度为25μm,实现了中子转换层厚度优化。利用^(241)Amα放射源(活度9.37×10^(3)Bq)开展α粒子响应信号幅度的测量,并在^(137)Csγ放射源(活度6.23×10^(7)Bq)环境下开展γ射线的响应测试。另外,在标准辐射场系统中进行了SiC探测器的中子注量率响应线性度测量、γ剂量率响应线性度测量以及中子注量率响应线性标定。结果表明:该探测器在1×10^(3)~1×10^(6)cm^(−2)·s^(−1)中子注量率范围内线性响应拟合R^(2)=0.9969,具有良好的线性响应,n/γ剂量响应范围为0.005~20 Gy∙h^(−1),可用于核电现场反应堆中子和γ剂量的实时、精确监测。

基于台山核电厂中子剂量监测实践的思考

介绍了台山核电厂近几年来开展的中子辐射监测以及中子剂量监测的相关实践,并基于实践情况开展了中子剂量监测的合规性分析,讨论了国内外法规和标准针对核电厂中子剂量监测的要求。分析认为,台山核电厂近年来对中子辐射开展的剂量监测实践符合国内相关法规和标准的要求,但是也发现目前国内针对核电厂中子辐射监测的法规和标准中未明确需要开展中子个人剂量监测的起测标准,国际原子能机构的一般安全导则以及国外部分国家在核电厂中子剂量监测方面有相对更明确的规定。建议我国相关部门针对核电厂中子剂量监测考虑补充相关指导条款,各核电厂应针对自身情况开展中子剂量监测评价。

TEPC及其中子剂量测量应用研究进展

基于组织等效正比计数器(Tissue-Equivalent Proportional Counter,TEPC)的辐射监测装置在中子周围剂量当量测量领域展现出独特优势和应用潜力,成为各国新型中子剂量测量技术的研究热点。本文阐述了TEPC基本工作原理、各种技术路线的工作机理和特点优势,综述了基于TEPC的中子周围剂量当量测量技术的国内外研究和应用现状,并对关键技术的未来发展进行了展望。

Activation and shutdown dose-rate analyses for the EAST NBI test facility

An analysis of the neutron activation and shutdown dose rates was performed for the EAST high-power deuterium neutral beam injector test facility(EAST NBITF) by using the multiparticle transport code FLUKA2011.2. Also, the neutron and neutron-induced gamma spectra of the facility's vacuum vessel were evaluated. The results identified the major radionuclides^(99) Mo,^(65)Ni,^(58) Co,^(56)Mn, and^(51) Cr for the vacuum vessel and the primary nuclide^(64) Cu for both the ion dump and the calorimeter.The simulated results indicated that, when the EAST NBITF operates within the design parameters of deuterium energy 80 ke V, current 50 A, and pulse 100 s, the neutron intensity will achieve 10^(11)n/s with no radiation safety problems after the EAST NBITF shuts down.

Simulation of radiation dose distribution and thermal analysis for the bulk shielding of an optimized molten salt reactor

The Chinese Academy of Science has launched a thorium-based molten-salt reactor(TMSR)research project with a mission to research and develop a fission energy system of the fourth generation.The TMSR project intends to construct a liquid fuel molten-salt reactor(TMSR-LF),which uses fluoride salt as both the fuel and coolant,and a solid fuel molten-salt reactor(TMSR-SF),which uses fluoride salt as coolant and TRISO fuel.An optimized 2 MWth TMSR-LF has been designed to solve major technological challenges in the Th-U fuel cycle.Preliminary conceptual shielding design has also been performed to develop bulk shielding.In this study,the radiation dose and temperature distribution of the shielding bulk due to the core were simulated and analyzed by performing Monte Carlo simulations and computational fluid dynamics(CFD)analysis.The MCNP calculated dose rate and neutron and gamma spectra indicate that the total dose rate due to the core at the external surface of the concrete wall was 1.91μSv/h in the radial direction,1.16μSv/h above and 1.33μSv/h below the bulk shielding.All the radiation dose rates due to the core were below the design criteria.Thermal analysis results show that the temperature at the outermost surface of the bulk shielding was 333.86 K,which was below the required limit value.The results indicate that the designed bulk shielding satisfies the radiation shielding requirements for the 2 MWth TMSR-LF.

Experimental test of a new neutron threshold detector and its application

The possibility of using 209Bi as a new threshold detector to measurc high-energy neutrons was investigated for the first time. At the same time the experiment measured successfully the emitted neutron fiuence rate, energy spectrum and dose equivalent rate distributions in the heavy ion target area using a detector complex including 209Bi, 115In, 27A1, 19F and 12C samples.

Synergistic effects of neutron and gamma ray irradiation of a commercial CHMOS microcontroller

This paper presents the experimental results of a combined irradiation environment of neutron and gamma rays on 80C196KC20, which is a 16-bit high performance member of the MCS96 microcontroller family. The electrical and functional tests were made in three irradiation environments： neutron, gamma rays, combined irradiation of neutron and gamma rays. The experimental results show that the neutron irradiation can affect the total ionizing dose behaviour. Compared with the single radiation environment, the microcontroller exhibits considerably more severe degradation in neutron and gamma ray synergistic irradiation. This phenomenon may cause a significant hardness assurance problem.

Neutron distribution and yield produced by 50 MeV/u^(18)O-ion on thick targets

Neutron energy, fluence rate, angular distributions and dose equivalent rate distributions around the thick Be, Cu, An targets bombarded by 50 MeV/u 18O-ion were measured using a threshold detector activation method. At the same time,the neutron yields of 18O-ion and the neutron emission rates in the forward direction were obtained approximately.

Neutron-induced apoptosis of HR8348 cells in vitro

INTRODUCTIONTo date ,the major therapy for rectal carcinoma is extensive abdomino-perineal resection[1]. Unfortunately ,after resection of rectal carcinoma ,many patients still die of blood-borne metastases ,usually in the liver or lungs ,or local prlvic recurrence[2,3],which is the major cause of morbidity and mortality in patients with rectal carcinoma .Pre-or postoperative radiotherapy can reduce the incidence of local rdcurrence[4-7].

Rem-meter correction factor for measuring high energyneutrons outside concrete shielding

Correction factors of both Rem-meters, the 10 inch diameter single-sphere Remmeter and the standard A-B Rem-meter, were estimated for measuring high energy neutron dose equivalent outside a concrete shielding wall and the effects that the emitted neutron spectra become remarkably "harder" penetrated through a concrete shielding wall, and the energy response of the Rem-meter were taken in account. The estimated results could be applied in the measurement of neutron dose equivalent for the intermediate energy heavy ion reactions to avoid the difficulty induced by the energy response of the Rem-meters.

Neutrons produced by 75 MeV/u ^(12)C-ion on thick targets

Fluence rates and angular distributions of the neutron emitted by75 MeV/u 12C-ion bombardment on thick Be and An targets have been measured bymeans of the threshold detector activation method. Based on that, the neutron yields,emission rates in the forward direction and neutron dose equivalent rate distributionswere deduced.

Formation of Neutron Fields from Radionuclide Neutron Sources for Metrological Support of Dosimetric Quantities Measurements

The problems of formation of neutron fields are using the radionuclide neutron sources. Theoretical estimates of the contribution to the values of the neutron flux density, kerma and ambient dose equivalent scattered neutron radiation under various conditions of use of neutron sources. The coefficients for calculating the values of different variables at different distances from the source are using the measured values at certain distances from the source. The values of the average energies for neutron spectra are obtained using the radionuclide neutron sources.

The clinical practice of ^(252)Cf neutron brachytherapy devices on malignant tumor in China

The 252Cf neutron brachytherapy devices were designed and manufactured after solving those problems:the shield difficulties for 252Cf neutron;the method and facilities for 252Cf neutron source deliver;the dose calculation and measurement for 252Cf neutron.From 1999 to 2009,more than twenty 252Cf neutron brachytherapy devices had been installed in China.The Chinese radiation oncologists implemented the 252Cf neutron brachytherapy on more than 5 000 different kinds of cancer patients,including cervix cancer;endometrium cancer and achieved ideal results.For special presentation,they had breakthrough on radical treatment for low lying rectal adenocarcinoma with sphincter preservation and melanoma patients after the modification of 252Cf neutron intracavitary applicator and dose calibration.