Nuclear Analysis最新文献_第4页

Assessment of radiation shielding properties for some concrete mixtures against photon and neutron radiations 某些混凝土混合料对光子和中子辐射屏蔽性能的评价

Nuclear Analysis

Pub Date : 2025-03-01 DOI: 10.1016/j.nucana.2025.100152

Brahim EL Azzaoui , Ouadie Kabach , Younes EL Abbari , Mohamed Youssef Messous , Khalid Nabaoui , Rabie Outayad , Yassine EL Lkhadiri , El mahjoub ChAKIR , El Mehdi Alibrahmi

This study evaluates fifteen concrete formulations, including standard and hybrid types such as Barite, Iron-Limonite, and Luminite-Colemanite-Barite, to determine their effectiveness in shielding against photon rays and neutrons. Using computational tools like MCNP, Phy-X, and XCOM, key shielding parameters were analyzed, including the Mass Attenuation Coefficient, Half-Value Layer, Mean Free Path, Fast Neutron Removal Cross Section, and Neutron Transmittance. In photon shielding, Iron-Portland concrete demonstrated superior performance, achieving the lowest Half-Value Layer (HVL) of 2.244 cm at 1.33 MeV, which is 42 % better than Ordinary concrete and 57 % better than Barite concrete. Iron-Limonite also showed strong photon attenuation with a Mean Free Path (MFP) of 3.23 cm at 1.33 MeV. For neutron shielding, Iron-Limonite and Ferro-phosphorus concrete recorded the highest Fast Neutron Removal Cross Section (FNRCS) values, reaching up to 0.146 cm⁻¹, indicating their strong capability to attenuate fast neutrons. Additionally, hybrid concretes like Luminite-Colemanite-Barite provided balanced protection against both photon and neutron radiation. This study highlights the effectiveness of high-density concretes in radiation shielding and underscores the alignment between deterministic and stochastic computational tools used, reinforcing their applicability in enhancing radiation safety.

本研究评估了15种具体配方，包括标准和混合类型，如重晶石、铁-褐铁矿和发光- colemanite -重晶石，以确定其屏蔽光子射线和中子的有效性。利用MCNP、Phy-X和XCOM等计算工具，分析了主要屏蔽参数，包括质量衰减系数、半值层、平均自由程、快中子去除截面和中子透射率。在光子屏蔽方面，铁硅酸盐混凝土表现出优异的性能，在1.33 MeV下实现了2.244 cm的最低半值层（HVL），比普通混凝土高42%，比重晶石混凝土高57%。铁褐铁矿也表现出较强的光子衰减，在1.33 MeV下平均自由程（MFP）为3.23 cm。在屏蔽中子方面，铁-褐铁矿和磷铁混凝土的快中子去除截面（FNRCS）值最高，可达0.146 cm - 1，说明它们对快中子的衰减能力很强。此外，像luminite - colemanite -重晶石这样的混合混凝土提供了对光子和中子辐射的平衡保护。本研究强调了高密度混凝土在辐射屏蔽方面的有效性，并强调了所使用的确定性和随机计算工具之间的一致性，加强了它们在提高辐射安全方面的适用性。

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引用次数: 0

Assessment of metal contamination in sediment of Kerala Coast, India using EDXRF technique and Multivariate Statistical method 利用EDXRF技术和多元统计方法评价印度喀拉拉邦海岸沉积物中金属污染

Nuclear Analysis

Pub Date : 2024-12-21 DOI: 10.1016/j.nucana.2024.100151

T. Kiruba , P. Jayaprakash , J. Juliet Josephine Joy , J. Venkatamuthukumar , M. Suresh Gandhi , R. Ravisankar

The current study focused on the distribution of heavy metals in sediments from coastline of Kerala, India using Energy Dispersive X-ray Fluorescence (EDXRF) technique. The concentration of V, Cr, Mn, Cu, Zn, Ba, Rb, Zr, As, Br, Sr, and Pb was determined in the sediment samples. The extent of pollution to sediment was assessed via various pollution indices such as enrichment factor (EF), contamination factor (CF), geo accumulation index (I_geo), metal pollution load index (MPI), degree of contamination (Cd), modified contamination degree (mCd), and potential contamination index (Cp) based on the corresponding background values. The source of origin of heavy metals and the correlation amongst the studied elements was studied using multivariate analysis approach (Pearson correlation matrix, principal component analysis and cluster analysis). The Sediment Quality Guidelines (SQGs) was applied to understand the ecotoxicological significance of heavy metal toxicity. The observed concentration of heavy metals in the studied sediments is due to anthropogenic activity and also from the discharge of municipal wastewater, domestic sewage, fishing harbor activities, industrial and aquaculture pollutants. A regular surveillance and remedial measures for contaminant discharge may reduce the metal content in the study area.

利用能量色散x射线荧光（EDXRF）技术对印度喀拉拉邦海岸线沉积物中重金属的分布进行了研究。测定了沉积物样品中V、Cr、Mn、Cu、Zn、Ba、Rb、Zr、As、Br、Sr、Pb的浓度。基于相应的背景值，通过富集系数（EF）、污染系数（CF）、地质累积指数（Igeo）、金属污染负荷指数（MPI）、污染程度（Cd）、修正污染程度（mCd）、潜在污染指数（Cp）等污染指标评价沉积物污染程度。采用多变量分析方法（Pearson相关矩阵、主成分分析和聚类分析）研究重金属的来源及各元素之间的相关性。应用沉积物质量指南（SQGs）了解重金属毒性的生态毒理学意义。所研究沉积物中观察到的重金属浓度是由于人为活动造成的，也来自城市废水、生活污水、渔港活动、工业和水产养殖污染物的排放。污染物排放的定期监测和补救措施可以降低研究区域的金属含量。

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引用次数: 0

The influence of reactor hall on the measurement of reactivity using prompt neutron method 反应炉大厅对瞬发中子法测定反应性的影响

Nuclear Analysis

Pub Date : 2024-12-16 DOI: 10.1016/j.nucana.2024.100150

Hui Gao, Meng Li

In response to the phenomenon of deviation between reactivity measurement values and expected values observed in pulsed reactor experiments, the reactivity measurement process in fission pulse experiments was simulated. The phenomenon of low measurement values by the prompt neutron method has been reproduced. It was found that the return of reflected neutrons is delayed and dispersed, and some reflected neutrons did not return in time during the reactivity measurement process, resulting in low reactivity measurement values. Therefore, the measurement values obtained by the prompt neutron method need to be corrected in some cases.

针对脉冲堆实验中观察到的反应性测量值与期望值存在偏差的现象，对裂变脉冲实验中的反应性测量过程进行了模拟。再现了瞬发中子法测量值低的现象。研究发现，在反应性测量过程中，反射中子的返回存在延迟和分散现象，部分反射中子没有及时返回，导致反应性测量值偏低。因此，在某些情况下，用提示中子法得到的测量值需要进行校正。

引用次数: 0

Correlation between microscopic degradation mechanism and macroscopic mechanical property of epoxy resin based on low molecular weight radiolysis products 基于低分子量辐射解产物的环氧树脂微观降解机理与宏观力学性能的关系

Nuclear Analysis

Pub Date : 2024-12-01 DOI: 10.1016/j.nucana.2024.100143

Lei Yu , Shuai Chen , Jianming Zhou , Shuai Liu , Bo Liu , Jing Peng , Shuo Hou , Yinyong Ao

Low molecular weight radiolysis products play an important role in the performance change and degradation mechanism of polymer materials. In this study, the radiolysis products with low molecular weight of epoxy resin were detected, identified and quantified through solid phase microextraction combined with gas chromatography-mass spectrometry (SPME-GC-MS). The qualitative results showed that most of radiolysis products of epoxy resin were phenols and ketones. The result of principal component analysis showed that the composition of radiolysis products produced at different absorbed doses had obvious difference, indicating that the degradation degree of epoxy resin was different at different absorbed dose. Phenol can be used as an indicator product to reflect the change of tensile strengrh. It indicated that the identification of the radiolysis products was useful for studying the degradation mechanisms and predicting the degradation degree of epoxy resin. Accordingly, the radiation-induced degradation mechanisms were proposed according to the radiolysis products and theoretical calculations.

低分子量辐射解产物在高分子材料的性能变化和降解机理中起着重要作用。本研究采用固相微萃取-气相色谱-质谱联用技术（SPME-GC-MS）对低分子量环氧树脂的放射性溶解产物进行检测、鉴定和定量。定性结果表明，环氧树脂的辐射分解产物以酚类和酮类为主。主成分分析结果表明，不同吸收剂量下产生的放射性溶解产物组成有明显差异，说明不同吸收剂量下环氧树脂的降解程度不同。苯酚可作为反映抗拉强度变化的指标产品。结果表明，对放射性降解产物的鉴定有助于研究环氧树脂的降解机理和预测其降解程度。据此，根据辐射分解产物和理论计算，提出了辐射诱导降解机理。

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引用次数: 0

New single-toroidal sintered diamond anvil and assembly for high pressure neutron diffraction 用于高压中子衍射的新型单环烧结金刚石砧及组件

Nuclear Analysis

Pub Date : 2024-11-08 DOI: 10.1016/j.nucana.2024.100142

Leiming Fang, Gongzhang Yang, Guoliang Niu, Ruiqi He, Jiacheng Sun, Xiping Chen, Lei Xie

In-situ high pressure neutron diffraction experiments, which require a large volume samples, remain challenging, particularly when generating simultaneous high pressure-temperature (P-T) conditions. Although high pressure neutron diffraction experiments have been successfully extended to pressures exceeding 20 GPa, generating pressures over 10 GPa with a large sample volume in the millimeter scale is still difficult. Based on the strategy of introducing gaskets in multi-anvil press, a new single-toroidal sintered diamond anvil and high P-T assembly have been designed for use in the Paris-Edinburgh press, to promoting the neutron diffraction technique with a broadened P-T range. This new single-toroidal set-up can achieve pressure exceeding 14 GPa, with a pressure generating efficiency is nearly same as that of double-toroidal anvil, and exhibits remarkable stability during high P-T experiments. The high P-T neutron diffraction experiments demonstrate that the new set-up can achieves a pressure of 8.7(1) GPa and a temperature of 1380(15) K with a large sample volume of 38 mm³.

需要大量样品的原位高压中子衍射实验仍然具有挑战性，特别是在同时产生高压-温度（P-T）条件时。虽然高压中子衍射实验已经成功地扩展到超过20gpa的压力，但在毫米尺度上产生大于10gpa的压力和大样本量仍然是困难的。基于在多砧压机中引入衬垫的策略，设计了一种新的单环烧结金刚石砧和高P-T组件，用于巴黎-爱丁堡压机，以促进中子衍射技术的P-T范围的扩大。这种新的单环面装置可以获得超过14 GPa的压力，其产生压力的效率几乎与双环面砧相同，并且在高P-T实验中表现出显著的稳定性。高P-T中子衍射实验表明，新装置可以实现压力为8.7(1)GPa，温度为1380(15)K，样品体积为38 mm3。

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引用次数: 0

Investigation of photon interaction parameters in Human Body Tissues using GAMOS, FLUKA, and XCOM Studies 利用 GAMOS、FLUKA 和 XCOM 研究调查人体组织中的光子相互作用参数

Nuclear Analysis

Pub Date : 2024-10-15 DOI: 10.1016/j.nucana.2024.100141

A. Arectout , H. Boukhal , M. Jarmouni , K. Laazouzi , M. Assalmi , A. Nouayti , M. Hadouachi , H. El Yaakoubi , E. Chakir

This study aims to evaluate different photon interaction parameters of human body organs at nine photon energies (0.021 keV–1.25 MeV) using GAMOS and FLUKA Monte Carlo codes. The Mass attenuation coefficients, Mean Free Path, Half Value Layer, Tenth Value Layer, and Mass absorption coefficients of the breast, lung, kidney, pancreas, liver, eye lens, thyroid, brain, ovary, heart, large intestine blood, skin, spleen, muscle, and cortical bone were investigated and compared against the standard values available from the tables of XCOM database. This comparison demonstrated a good agreement, with all calculated values deviating less than 6 %. In addition, the values obtained with the GAMOS code were similar to those obtained using the FLUKA code. These comparisons indicate very good agreement and revealed that both FLUKA and GAMOS codes can be used as a computational tool for determining the photon interaction parameters of any material and also different energies, whose data are not available in the literature.

本研究旨在使用 GAMOS 和 FLUKA 蒙特卡洛代码评估人体器官在九种光子能量（0.021 keV-1.25 MeV）下的不同光子相互作用参数。研究了乳腺、肺、肾、胰腺、肝、眼晶状体、甲状腺、脑、卵巢、心脏、大肠血液、皮肤、脾脏、肌肉和皮质骨的质量衰减系数、平均自由路径、半值层、十值层和质量吸收系数，并与 XCOM 数据库表格中的标准值进行了比较。比较结果表明，所有计算值的偏差均小于 6%，一致性良好。此外，使用 GAMOS 代码获得的值与使用 FLUKA 代码获得的值相似。这些比较结果表明两者的一致性非常好，并揭示出 FLUKA 和 GAMOS 代码都可以作为一种计算工具，用于确定任何材料的光子相互作用参数以及不同能量的光子相互作用参数，而这些参数的数据在文献中是没有的。

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引用次数: 0

Optimizing neutron shielding: A specialised container approach for Disused Sealed Radioactive Sources and orphan neutron emitters 优化中子屏蔽：废弃密封放射源和无主中子发射器的专用容器方法

Nuclear Analysis

Pub Date : 2024-10-10 DOI: 10.1016/j.nucana.2024.100140

Brahim EL Azzaoui , Ouadie Kabach , Mohamed Youssef Messous , El mahjoub Chakir , El Mehdi Alibrahmi

Shielding Disused Sealed Radioactive Sources (DSRSs) and orphan neutron sources, such as ²⁵²Cf, pose challenges due to the high penetration of neutrons, induced radioactivity in shielding materials, and the limited availability of compact, effective shielding materials. This study addresses these challenges by proposing a specialized container for the safe transport, conditioning, and disposal of neutron-emitting DSRSs and orphan sources. The computational tool that was used in this study is the Monte Carlo N-Particle (MCNP). The investigation begins with an examination of moderation materials, including high-density polyethylene (HDPE), paraffin, and water-extended polyester (WEP). Subsequently, four concrete types, namely Ordinary, Barite, Portland, and Serpentine Concrete, are scrutinized. Employing a comprehensive methodology, the design of the container is optimized to effectively moderate and absorb neutron emissions. The findings of this study demonstrate that the designed compact container can safely handle activities exceeding those studied, effectively managing up to 10 μg (about 0.2 GBq) ²⁵²Cf without exceeding 25 μSv/h at the outer container contact. This suggests a promising solution for the secure management of high-activity neutron-emitting sources.

屏蔽废弃密封放射源（DSRS）和无主中子源（如 252Cf）是一项挑战，原因在于中子的高穿透性、屏蔽材料中的诱导放射性以及紧凑、有效屏蔽材料的有限性。本研究针对这些挑战，提出了一种用于安全运输、调节和处置发射中子的 DSRS 和无主源的专用容器。本研究使用的计算工具是蒙特卡罗 N 粒子（MCNP）。研究首先考察了缓和材料，包括高密度聚乙烯（HDPE）、石蜡和水膨胀聚酯（WEP）。随后，仔细研究了四种混凝土类型，即普通混凝土、重晶石混凝土、硅酸盐混凝土和蛇纹石混凝土。采用综合方法对容器的设计进行了优化，以有效缓和并吸收中子辐射。研究结果表明，所设计的紧凑型容器可以安全地处理超出研究范围的活动，有效地管理高达 10 μg（约 0.2 GBq）252Cf，而在容器外部接触处不会超过 25 μSv/h。这为高活性中子发射源的安全管理提供了一个前景广阔的解决方案。

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引用次数: 0

A comparative analysis of the NaI detector response function using GAMOS and FLUKA Monte Carlo simulations 利用 GAMOS 和 FLUKA 蒙特卡罗模拟对碘化钠探测器响应函数进行比较分析

Nuclear Analysis

Pub Date : 2024-09-23 DOI: 10.1016/j.nucana.2024.100138

A. Arectout , H. Boukhal , E. Chakir , M. Jarmouni , M. Assalmi , T. El Ghalbzouri , O.E. Belhaj , Mohamed Drissi El-Bouzaidi , A. Nouayti , I. Zidouh , H. El Yaakoubi

This work aims to study the response function of a 2″×2″ NaI(Tl) scintillation detector using Monte Carlo simulations. A precise mathematical model of the NaI(Tl) scintillator was developed using both FLUKA and GAMOS Monte Carlo simulation software. The photon pulse height distributions of the NaI(Tl) without influence of its energy resolution, obtained with FLUKA and GAMOS codes, were converted into a real NaI(Tl) response function using the necessary conversion process. Spectral characteristics such as full-energy peak efficiency, energy resolution, peak-to-Compton ratio, and peak-to-total ratio were investigated by simulation at different gamma-ray energy obtained from ¹⁰⁹Cd, ¹³⁷Cs, ⁵⁴Mn, ⁶⁵Zn, and ⁶⁰Co sources. The simulated spectra from the GAMOS code were consistent with those generated by the FLUKA code. Additionally, the comparison between simulated results and experimental data demonstrated good agreement. The validation of the computational models used for the NaI(Tl) detector in both FLUKA and GAMOS software was successfully achieved, confirming the accuracy of the simulations in replicating the detector's response.

这项工作旨在利用蒙特卡罗模拟研究 2″×2″ NaI（Tl）闪烁探测器的响应函数。利用 FLUKA 和 GAMOS 蒙特卡罗模拟软件建立了 NaI(Tl)闪烁体的精确数学模型。利用 FLUKA 和 GAMOS 代码获得的不受能量分辨率影响的 NaI（Tl）光子脉冲高度分布，通过必要的转换过程转换为真实的 NaI（Tl）响应函数。通过模拟从 109Cd、137Cs、54Mn、65Zn 和 60Co 源获得的不同伽马射线能量，研究了全能峰值效率、能量分辨率、峰值与康普顿比和峰值与总比等光谱特性。GAMOS 代码模拟的光谱与 FLUKA 代码生成的光谱一致。此外，模拟结果与实验数据的比较也显示出良好的一致性。在 FLUKA 和 GAMOS 软件中对 NaI(Tl)探测器所用计算模型的验证已成功实现，证实了模拟在复制探测器响应方面的准确性。

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引用次数: 0

Coulomb interaction dependence of optimal energy to synthesize superheavy elements 合成超重元素的最佳能量与库仑相互作用的关系

Nuclear Analysis

Pub Date : 2024-09-21 DOI: 10.1016/j.nucana.2024.100137

H.C. Manjunatha , N. Sowmya , K.N. Sridhar

The production of superheavy elements beyond Z

=

118 remains unattained through both cold and hot fusion techniques, primarily due to inadequate fusion reaction optimization involving projectile–target combinations and energy. Past efforts employed various theories to optimize these combinations. In our current study, we have successfully identified optimal fusion energies for synthesizing superheavy elements, employing an advance statistical model and dinuclear system models. The establishment of optimal energy governing rule is achieved through a comprehensive examination of the Coulomb interaction parameter, enabling precise determination of the optimal energy for successful fusion reactions in synthesizing superheavy elements. The confidence level of predicting optimal energies using the present formula varies between 97% to 99%. The predicted optimal energy using the present formula for five fusion reactions such as ²⁰⁸Pb(⁵⁰Ti,1n)²⁵⁷Rf, ²⁰⁸Pb(⁵⁰Ti,2n)²⁵⁶Rf, ²⁰⁹Bi(⁵⁰Ti,1n)²⁵⁸Db, ²⁰⁸Pb(⁵⁸Fe,1n)²⁶⁵Hs, and ²⁴⁴Pu(⁴⁸Ca,4n)²⁸⁸Fl were studied and are in good agreement with each other. Furthermore, we predicted the Optimal energies for fusion reactions leading to synthesize the superheavy element Z

=

119 and 120. The presented empirical rule will certainly bring a revolution in the synthesis of superheavy elements.

通过冷核聚变和热核聚变技术仍无法生产 Z = 118 以上的超重元素，这主要是由于涉及射弹-目标组合和能量的核聚变反应优化不足。过去的工作采用了各种理论来优化这些组合。在目前的研究中，我们利用先进的统计模型和双核系统模型，成功地确定了合成超重元素的最佳聚变能量。通过对库仑相互作用参数的全面研究，建立了最佳能量调控规则，从而精确确定了成功合成超重元素的最佳聚变反应能量。使用本公式预测最佳能量的置信度在 97% 到 99% 之间。我们对 208Pb(50Ti,1n)257Rf、208Pb(50Ti,2n)256Rf、209Bi(50Ti,1n)258Db、208Pb(58Fe,1n)265Hs 和 244Pu(48Ca,4n)288Fl 等五个聚变反应使用本公式预测的最佳能量进行了研究，结果相互吻合。此外，我们还预测了导致合成超重元素 Z = 119 和 120 的核聚变反应的最佳能量。所提出的经验法则必将为超重元素的合成带来一场革命。

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引用次数: 0

Electrodeposition of actinides: Optimization of deposition parameters by chronoamperometric studies 锕系元素的电沉积：通过计时器研究优化沉积参数

Nuclear Analysis

Pub Date : 2024-09-14 DOI: 10.1016/j.nucana.2024.100136

Fabiola Monroy-Guzmán, Luis Escobar Alarcón

To quantify alpha-emitting radionuclides by alpha spectrometry, it is necessary to prepare a thin and uniform alpha source on a suitable substrate. Electrodeposition is the most used electrochemical technique for this purpose. In order to better understand the electrochemical process carried out in the electrodeposition of actinides, in particular the selection of the current densities applied, a chronoamperometric study of the electrodeposition of actinides (Th, U, Pu, Am and Cm), in three different electrolytes (Na₂SO₄/H₂SO₄, NH₄NO₃, NaF) using stainless steel and platinum as cathode and anode, respectively, is presented. The corresponding polarization curves (potential vs. current density), characteristic for each electrolyte and actinide used, were constructed from the chronoamperometric data. The limiting diffusion current as well as the minimum current necessary for the electrodeposition process to take place were determined. To achieve a quantitative electrodeposition of actinides, a balance between OH⁻ production and the thickness of the OH⁻ layer formed near the cathode must be reached. These parameters are controlled by the electrolyte used and the current density applied to the electrochemical system. Actinides were electrodeposited mainly in the form of oxides, according to Raman spectroscopy results.

要通过α光谱法量化α放射性核素，就必须在合适的基底上制备薄而均匀的α源。为此，电沉积是最常用的电化学技术。为了更好地了解锕系元素电沉积过程中的电化学过程，特别是电流密度的选择，本文介绍了在三种不同的电解质（Na2SO4/H2SO4、NH4NO3、NaF）中，以不锈钢和铂分别作为阴极和阳极，对锕系元素（Th、U、Pu、Am 和 Cm）的电沉积过程进行的时变研究。根据计时器数据构建了相应的极化曲线（电位与电流密度的关系），这是每种电解质和所用锕系元素的特征。确定了电沉积过程所需的极限扩散电流和最小电流。要实现锕系元素的定量电沉积，必须在 OH- 生成和阴极附近形成的 OH- 层厚度之间达到平衡。这些参数受所用电解质和电化学系统电流密度的控制。根据拉曼光谱结果，锕系元素主要以氧化物的形式电沉积。

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引用次数: 0