Nuclear Technology & Radiation Protection最新文献_第4页

Analytical computation technique for calculation the effective geometrical solid angle and the efficiency of cubic scintillation crystal with side cylindrical hole 用解析计算方法计算带边圆柱孔的立方闪烁晶体的有效几何立体角和效率

IF 1.2 4区工程技术

Nuclear Technology & Radiation Protection Pub Date : 2022-01-01 DOI: 10.2298/ntrp2202091b

M. Badawi, A. Thabet

{"title":"Analytical computation technique for calculation the effective geometrical solid angle and the efficiency of cubic scintillation crystal with side cylindrical hole","authors":"M. Badawi, A. Thabet","doi":"10.2298/ntrp2202091b","DOIUrl":"https://doi.org/10.2298/ntrp2202091b","url":null,"abstract":"In the gamma-ray spectroscopy field, the radiometric examination for small quantities of natural samples is extremely significant. Therefore, the gamma-ray spectrometry calibration process must be prepared with good precision for several energies, matrices of sources or samples, and source-to-detector shapes. This manuscript considers a new uncomplicated analytical computation technique to calculate the effective geometrical solid angle and the efficiency of cubic scintillation crystal with a side cylindrical hole. The computations can be done by using a simple method, with a few essential limitations, that describes radioactive point sources located inside the side cylindrical hole and a high-efficiency cubic NaI(Tl) detector, come together with a low background as well. The technique stands on a trouble-free solid angle analytical formula for the detection system, using an accurate relation for the detector cavity, united with rough formulas controlling the interactions in the gamma-ray source and the materials introduced in between the source and the gamma-ray spectrometry. This new technique is not restricted to certain sources, because several source shapes can correspond to a homogeneous huge number of point sources and the detector geometry can be represented as a set of border points. The technique simply can be useful to obtain the full-energy peak efficiency in the future, challenging developments for low-energy gamma-ray spectroscopy.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":"1 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68548260","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 2

Soil radon exhalation rate measurement in Duhok city by two techniques 两种技术测定杜鹤市土壤氡析出率

IF 1.2 4区工程技术

Nuclear Technology & Radiation Protection Pub Date : 2022-01-01 DOI: 10.2298/ntrp2203229a

W. Alhamdi, M. Abdullah

引用次数: 0

Investigation of photon doses reaching healthy tissues in the use of different neutron energies in boron neutron capture therapy 不同中子能量在硼中子俘获治疗中到达健康组织的光子剂量的研究

IF 1.2 4区工程技术

Nuclear Technology & Radiation Protection Pub Date : 2022-01-01 DOI: 10.2298/ntrp2204334t

T. Tuğrul

{"title":"Investigation of photon doses reaching healthy tissues in the use of different neutron energies in boron neutron capture therapy","authors":"T. Tuğrul","doi":"10.2298/ntrp2204334t","DOIUrl":"https://doi.org/10.2298/ntrp2204334t","url":null,"abstract":"Boron neutron capture therapy is a unique treatment method that aims to kill the tumor cells with the help of heavy particles. Particles resulting from the interaction of the tumor region containing 10B atoms with thermal or epithermal neutrons have the most important role in this treatment method. In this study, gamma radiation reaching healthy tissues, which is the result of 10B(n,a)7Li reaction, was investigated. A simulation suitable for boron neutron capture therapy treatment, including the human head model, was created by the Monte Carlo N-Particle (MCNP) program. By using five different neutron energies, the gamma radiations resulting from the 10B(n,a)7Li reaction in the determined regions, close to the tumor tissue, were investigated. It was observed that the healthy tissue between the tumor area and the surface is exposed to the highest gamma flux and the highest gamma radiation absorption. It was also observed that these values increase as neutron energy decreases. It was found that the gamma doses received by some regions outside the neutron irradiation area could be significant. It has been understood that the change in neutron energy may cause significant changes in gamma radiation values reaching healthy tissues, especially in regions close to the surface. In boron neutron capture therapy treatments, the neutrons sent to the tumor should be selected depending on the location of the tumor and the size of the tumor area. This study contains significant data about photon doses in healthy tissues around the brain region treated using different neutron energies with the boron neutron capture therapy technique.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":"1 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68550511","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Impact of stringent tolerance criteria on verification of absorbed dose distributions and evaluation through inhomogeneous media 严格的耐受标准对非均匀介质吸收剂量分布验证和评价的影响

IF 1.2 4区工程技术

Nuclear Technology & Radiation Protection Pub Date : 2022-01-01 DOI: 10.2298/ntrp2202138o

N. Obajdin, Djeni Smilovic-Radojcic, David Rajlić, Manda Švabić-Kolacio, S. Jurković

{"title":"Impact of stringent tolerance criteria on verification of absorbed dose distributions and evaluation through inhomogeneous media","authors":"N. Obajdin, Djeni Smilovic-Radojcic, David Rajlić, Manda Švabić-Kolacio, S. Jurković","doi":"10.2298/ntrp2202138o","DOIUrl":"https://doi.org/10.2298/ntrp2202138o","url":null,"abstract":"Advances of radiation delivery devices have increased the complexity of the radiation oncology treatments. Herewith, outcome of the treatment, as well as patient safety, strongly depend on the consistency of absorbed dose delivery. Both can be ensured by comprehensive system of verification of calculated absorbed dose distributions. Standard method is evaluation of calculated absorbed dose distribution according to gamma method, using a 2-D detector and a homogeneous phantom, to obtain measured dose distribution. Purpose of this research was to investigate the influence of tolerance criteria on gamma passing rate. Additionally, the agreement in heterogeneous phantom was analysed. Absorbed dose calculations were performed using systems Monaco and XiO. Detector with 1020 ionization chambers in homogeneous phantom and semi-anthropomorphic phantom was used for measurements. Absorbed dose distributions of around 3500 patients were analysed using gamma method. In homogeneous phantom, average gamma passing rates were within tolerance for 3 %/2 mm. For measurements in heterogeneous media, the highest average gamma passing rate was obtained for small volumes of medium treatment complexity (??=93.84%), while large volumes of treatment with low complexity yielded the lowest gamma passing rates (??= 83.22%).","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":"1 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68548825","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Research on leak monitoring of the primary circuit of a pressurized water reactor based on the 13N coincidence method 基于13N重合法的压水堆一次回路泄漏监测研究

IF 1.2 4区工程技术

Nuclear Technology & Radiation Protection Pub Date : 2022-01-01 DOI: 10.2298/ntrp2204308z

Yue Zhao, G. Qu, Jian Zhou

引用次数: 0

Developing a reliable approach to estimate the stoichiometric ratio of O/U in UO2 pellets using MCNP-5 and artificial intelligence 利用MCNP-5和人工智能开发一种可靠的方法来估计UO2颗粒中O/U的化学计量比

IF 1.2 4区工程技术

Nuclear Technology & Radiation Protection Pub Date : 2022-01-01 DOI: 10.2298/ntrp2204302s

S. Shaban, Ahmad Agha, Karim Aladham

{"title":"Developing a reliable approach to estimate the stoichiometric ratio of O/U in UO2 pellets using MCNP-5 and artificial intelligence","authors":"S. Shaban, Ahmad Agha, Karim Aladham","doi":"10.2298/ntrp2204302s","DOIUrl":"https://doi.org/10.2298/ntrp2204302s","url":null,"abstract":"Uranium dioxied is used as a nuclear fuel. Depending on the temperature and oxygen partial pressure, it is incredibly versatile and can accept a wide variety of stoichiometry. Many methods are used to estimate the non-stoichiometric O/U ratio such as the coulometric titration, gravimetric and voltammetric methods. These methods have some disadvantages and may be time and cost-consuming. This work develops an approach to determine the stoichiometric ratio by using MCNP-5 code and hyper pure germanium detector to estimate the count rate at 185.7 keV for UO2 pellets. The studied pellets are proposed to have 235U mass content (3 %, 4 %, and 5 %) and 1 cm away from the detector. The mass of the oxide within the pellets is 7.8995 grams. The relation between volume and density has been studied during different steps in which temperature increases. Finally, a reliable model is established to describe the process of converting green pellets to sintered pellets. The model is supported by employing artificial intelligence to predict some features and the overall correlation equals 0.99929.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":"1 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68550834","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Design of array switching circuit for multiplex nuclear pulse signal 多路核脉冲信号阵列开关电路的设计

IF 1.2 4区工程技术

Nuclear Technology & Radiation Protection Pub Date : 2022-01-01 DOI: 10.2298/ntrp2204321l

Qi Liu, Haitao Wang, Hailei Chen, Ren-Bo Wang

{"title":"Design of array switching circuit for multiplex nuclear pulse signal","authors":"Qi Liu, Haitao Wang, Hailei Chen, Ren-Bo Wang","doi":"10.2298/ntrp2204321l","DOIUrl":"https://doi.org/10.2298/ntrp2204321l","url":null,"abstract":"Commercial multi-channel energy spectrometers have good performance, they have multiple input signal channels and multi-channel analyzers, which can simultaneously acquire the energy spectrum of multiple nuclear pulse signals. But the input signal channel of this general multi-channel energy spectrometer cannot be switched between the internal multi-channel analyzers, and an input signal channel can only be fixed to the corresponding multi-channel analyzers. Hence, to resolve this issue, this paper designed a nuclear pulse signal array switching circuit. The core of the array switching circuit is a switch array chip with low internal resistance and high bandwidth, which controls the signal connection between the input signal channel with the multi-channel analyzers. Using 137Cs and uranium ore as radioactive sources, the energy spectrum test and spectrum data analysis were carried out using a NaI detector, respectively, when the nuclear pulse signal passed through and did not pass through the array switching circuit. The results showed that the circuit demonstrates little effect on the energy resolution and linearity of the multi-channel analyzers but causes a small drift of the high-energy photopeak, and improve the reliability of the circuit by energy spectrum data accumulation. This circuit can make the application of a multi-channel energy spectrometers more flexible and reliable.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":"1 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68550426","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 1

Simulation analysis and experiment of magnetic pole shape influence on betatron magnetic field 磁极形状对电子加速器磁场影响的仿真分析与实验

IF 1.2 4区工程技术

Nuclear Technology & Radiation Protection Pub Date : 2022-01-01 DOI: 10.2298/ntrp2201001l

Qi Liu, Ren-Bo Wang, Jin-Hai Li, Haitao Wang, Hailei Chen, Bin Tang

{"title":"Simulation analysis and experiment of magnetic pole shape influence on betatron magnetic field","authors":"Qi Liu, Ren-Bo Wang, Jin-Hai Li, Haitao Wang, Hailei Chen, Bin Tang","doi":"10.2298/ntrp2201001l","DOIUrl":"https://doi.org/10.2298/ntrp2201001l","url":null,"abstract":"Betatrons have the advantages of small size, lightweight, and simple operation. They are widely used in non-destructive testing, cargo, and vehicle safety inspection systems. Magnetic field distribution is an essential parameter of betatrons and has been investigated via experimental methods. Recently, simulations have been performed for the magnetic field distribution generated by different magnetic pole parameters. In this study, the finite element method is employed to simulate the magnetic field distribution. The effects of the different magnetic end face opening angles, pole protrusion sizes, number of central magnetic pads, and magnetic pole bottom width on the magnetic field distribution are simulated. Based on the simulation results, magnetic poles are developed, and the magnetic field distribution is measured by a gauss meter. The relative error of the measured and simulated equilibrium orbit is 2.1 %, and the relative error of the magnetic field decay index is 3.3 %. The magnetic field distribution can satisfy the essential conditions that the magnetic field at equilibrium orbit of the betatron is equal to half of the average magnetic field within equilibrium orbit and the magnetic field decay index is greater than 0 and less than 1. The results show that the finite element simulation method and established model have high reliability and effectively improve the design accuracy of magnetic poles.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":"1 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68547875","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Study on kinetic parameters characteristics of pebble bed reactor using HTR-proteus facility HTR-proteus装置球床反应器动力学参数特性研究

IF 1.2 4区工程技术

Nuclear Technology & Radiation Protection Pub Date : 2022-01-01 DOI: 10.2298/ntrp2202119z

Z. Zuhair, W. Luthfi, S. Sriyono, S. Suwoto, T. Setiadipura

{"title":"Study on kinetic parameters characteristics of pebble bed reactor using HTR-proteus facility","authors":"Z. Zuhair, W. Luthfi, S. Sriyono, S. Suwoto, T. Setiadipura","doi":"10.2298/ntrp2202119z","DOIUrl":"https://doi.org/10.2298/ntrp2202119z","url":null,"abstract":"The inherent safety feature of a pebble-bed reactor can be observed from its kinetic parameters. Proper modeling for calculating the reactor kinetic is also a concern for safe operation during normal and transient conditions. This study is intended to investigate the kinetic parameters characteristics of a pebble bed reactor using HTR-Proteus. A series of calculations were conducted using MCNP6 code and ENDF/B-VII library. The calculation results show that the negative value on core temperature reactivity is affected dominantly by the Doppler broadening effect. Prompt neutron lifetime l and mean generation time ? are slightly changed due to an increase in fuel temperature, moderator, and reflector that changed the neutron moderation and absorption over this part of the reactor. For (Th, U)O2, UO2, and PuO2 cores, the effective delayed neutron fraction ?eff values are more influenced by 233U, 235U, and 239Pu, respectively. In terms of stability during reactivity insertion, the UO 2 core is more stable and easier to control because its ?eff value is the largest compared to (Th,U)O2 and PuO 2 cores. It can be concluded that temperature must be controlled because it does not only affect the reactivity but also kinetic parameters as part of developing inherent safety features on the pebble-bed reactor.","PeriodicalId":49734,"journal":{"name":"Nuclear Technology & Radiation Protection","volume":"1 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"68548108","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Absorbed dose distribution in human eye simulated by FOTELP-VOX code and verified by volumetric modulated arc therapy treatment plan 用FOTELP-VOX代码模拟人眼吸收剂量分布，并用体积调制电弧治疗方案进行验证

IF 1.2 4区工程技术

Nuclear Technology & Radiation Protection Pub Date : 2022-01-01 DOI: 10.2298/ntrp2201078z

Milena Živković, T. Miladinović, A. Miladinović, Una Molnar, D. Krstić

引用次数: 1