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New Measurements of Photoneutron Spectra investigating specific signatures of Carbon, Nitrogen, and Oxygen
IF 2.9 3区 物理与天体物理 Q3 CHEMISTRY, PHYSICAL Pub Date : 2025-01-23 DOI: 10.1016/j.radphyschem.2025.112566
C. Besnard-Vauterin, B. Rapp, V. Blideanu
We report new measurements on photoneutron spectra from graphite, glucose, and melamine, revealing distinct signatures corresponding to carbon, oxygen, and nitrogen individual elements. Using a 23-MV electron linear accelerator (LINAC) and EJ-309 liquid scintillators with advanced pulse shape discrimination and pile-up rejection algorithms, we successfully detected fast neutrons from photo-nuclear (γ,Xn) reactions within an intense pulsed photon field. Energy deposition from fast neutrons was unfolded using two well-known independent algorithms ML-EM and GRAVEL. Our findings indicate discrepancies between the experimental results and Monte-Carlo simulations performed with the widely-used code MCNP6, highlighting the need for new data in order to improve the models used for the simulation of photoneutron production. These results have significant implications for various nuclear physics applications, including electron accelerator facilities decommissioning, illicit material detection for homeland security, and global radiotherapy patient dosimetry including neutron dose.
{"title":"New Measurements of Photoneutron Spectra investigating specific signatures of Carbon, Nitrogen, and Oxygen","authors":"C. Besnard-Vauterin, B. Rapp, V. Blideanu","doi":"10.1016/j.radphyschem.2025.112566","DOIUrl":"https://doi.org/10.1016/j.radphyschem.2025.112566","url":null,"abstract":"We report new measurements on photoneutron spectra from graphite, glucose, and melamine, revealing distinct signatures corresponding to carbon, oxygen, and nitrogen individual elements. Using a 23-MV electron linear accelerator (LINAC) and EJ-309 liquid scintillators with advanced pulse shape discrimination and pile-up rejection algorithms, we successfully detected fast neutrons from photo-nuclear (γ,Xn) reactions within an intense pulsed photon field. Energy deposition from fast neutrons was unfolded using two well-known independent algorithms ML-EM and GRAVEL. Our findings indicate discrepancies between the experimental results and Monte-Carlo simulations performed with the widely-used code MCNP6, highlighting the need for new data in order to improve the models used for the simulation of photoneutron production. These results have significant implications for various nuclear physics applications, including electron accelerator facilities decommissioning, illicit material detection for homeland security, and global radiotherapy patient dosimetry including neutron dose.","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"45 1","pages":""},"PeriodicalIF":2.9,"publicationDate":"2025-01-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143035261","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Computational neutron emission spectrometry and radiation assessment in VVER-1200 reactor nuclear fuel
IF 2.9 3区 物理与天体物理 Q3 CHEMISTRY, PHYSICAL Pub Date : 2025-01-23 DOI: 10.1016/j.radphyschem.2025.112555
Sergey V. Bedenko, Gennady N. Vlaskin, Sergey D. Polozkov, Ahmed H. Ali, Alexey A. Orlov, Hector Rene Vega-Carrillo
To ensure long-term and trouble-free operation, the reactor fuel is modified by introducing various homogeneous and heterogeneous additives. This modified fuels exhibit satisfactory performances under irradiation at elevated temperatures and burnup levels. However, the challenges related to radiation safety during the handling of fresh and spent nuclear fuel remain unresolved. In this study, neutron emission spectra and effective doses for VVER-1200 reactor fuel containing a heterogenous distribution of natGd2O3 and Am2O3, microspheres were calculated. Unlike in the case of homogenous variants, this design did not reduce the thermal conductivity of the fuel and positively affected the core neutronics and thermophysics. Comparing the radiation characteristics of fresh FAs revealed a considerable increase in the neutron (more than 3.7∙102 times at a distance of 10 cm from the FA) and photonic (about 104 times) components of Am–containing fuel compared to U and U–Gd fuels. The yield and effective dose of neutrons emitted from spent Am-containing fuel is two times higher than that of uranium–based fuels. When calculating the dose, it is important to consider the energy spectrum of (α, n) neutrons in Am2O2 microcapsules. The findings of this study provide insights into the development of procedures and regulations for manufacturing and post-irradiation handling of new fuel in reactors.
{"title":"Computational neutron emission spectrometry and radiation assessment in VVER-1200 reactor nuclear fuel","authors":"Sergey V. Bedenko, Gennady N. Vlaskin, Sergey D. Polozkov, Ahmed H. Ali, Alexey A. Orlov, Hector Rene Vega-Carrillo","doi":"10.1016/j.radphyschem.2025.112555","DOIUrl":"https://doi.org/10.1016/j.radphyschem.2025.112555","url":null,"abstract":"To ensure long-term and trouble-free operation, the reactor fuel is modified by introducing various homogeneous and heterogeneous additives. This modified fuels exhibit satisfactory performances under irradiation at elevated temperatures and burnup levels. However, the challenges related to radiation safety during the handling of fresh and spent nuclear fuel remain unresolved. In this study, neutron emission spectra and effective doses for VVER-1200 reactor fuel containing a heterogenous distribution of <ce:sup loc=\"post\">nat</ce:sup>Gd<ce:inf loc=\"post\">2</ce:inf>O<ce:inf loc=\"post\">3</ce:inf> and Am<ce:inf loc=\"post\">2</ce:inf>O<ce:inf loc=\"post\">3</ce:inf>, microspheres were calculated. Unlike in the case of homogenous variants, this design did not reduce the thermal conductivity of the fuel and positively affected the core neutronics and thermophysics. Comparing the radiation characteristics of fresh FAs revealed a considerable increase in the neutron (more than 3.7∙10<ce:sup loc=\"post\">2</ce:sup> times at a distance of 10 cm from the FA) and photonic (about 10<ce:sup loc=\"post\">4</ce:sup> times) components of Am–containing fuel compared to U and U–Gd fuels. The yield and effective dose of neutrons emitted from spent Am-containing fuel is two times higher than that of uranium–based fuels. When calculating the dose, it is important to consider the energy spectrum of (α, n) neutrons in Am<ce:inf loc=\"post\">2</ce:inf>O<ce:inf loc=\"post\">2</ce:inf> microcapsules. The findings of this study provide insights into the development of procedures and regulations for manufacturing and post-irradiation handling of new fuel in reactors.","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"3 1","pages":""},"PeriodicalIF":2.9,"publicationDate":"2025-01-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143035262","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Vibrational spectroscopy of Breast Tumor Phantoms: A novel approach to radiation dose estimation
IF 2.8 3区 物理与天体物理 Q3 CHEMISTRY, PHYSICAL Pub Date : 2025-01-23 DOI: 10.1016/j.radphyschem.2025.112556
Arslan Ahmad , Sahar Khalid , Muhammad Yousaf , Maria Atiq , Mahr un Nisa , Naima Amin

Purpose

This study aims to develop a simulated breast tumor model with the main objective of analyzing and designing treatment dosage delivery inside the malignant tissue and its nearby areas. Vibrational spectroscopy was employed to provide assistance in this measurement.

Materials and method

Using Fourier transform infrared (FTIR) study results, we confirmed that the phantom materials closely matched actual tumor tissues, with ingredients such as vegetable oil representing fats and lipids while gelatin simulating protein supplies. The presence of sodium chloride (NaCl) was implemented to augment conductivity.

Results

Characterization techniques confirmed the phantom's equivalence to real tumor tissues. X-ray diffraction (XRD) investigation revealed a strong peak indicating a highly crystalline structure, which was attributed to NaCl. Swelling and degradation experiments were used to validate water content equivalence and assess the phantom's durability. FTIR analysis indicated that ester bonds ruptured in the phantom during a 40 Gy radiation dosage, resembling alterations seen in breast tumor cell membranes after radiation exposure.

Conclusion

This phantom proves to be a valuable tool for evaluating cancer treatment strategies. The penetration of radiation in the breast cancer phantom will allow us to explore the effects of radiation on target cells. It will additionally help us in optimizing the radiation dose for breast cancer.
{"title":"Vibrational spectroscopy of Breast Tumor Phantoms: A novel approach to radiation dose estimation","authors":"Arslan Ahmad ,&nbsp;Sahar Khalid ,&nbsp;Muhammad Yousaf ,&nbsp;Maria Atiq ,&nbsp;Mahr un Nisa ,&nbsp;Naima Amin","doi":"10.1016/j.radphyschem.2025.112556","DOIUrl":"10.1016/j.radphyschem.2025.112556","url":null,"abstract":"<div><h3>Purpose</h3><div>This study aims to develop a simulated breast tumor model with the main objective of analyzing and designing treatment dosage delivery inside the malignant tissue and its nearby areas. Vibrational spectroscopy was employed to provide assistance in this measurement.</div></div><div><h3>Materials and method</h3><div>Using Fourier transform infrared (FTIR) study results, we confirmed that the phantom materials closely matched actual tumor tissues, with ingredients such as vegetable oil representing fats and lipids while gelatin simulating protein supplies. The presence of sodium chloride (NaCl) was implemented to augment conductivity.</div></div><div><h3>Results</h3><div>Characterization techniques confirmed the phantom's equivalence to real tumor tissues. X-ray diffraction (XRD) investigation revealed a strong peak indicating a highly crystalline structure, which was attributed to NaCl. Swelling and degradation experiments were used to validate water content equivalence and assess the phantom's durability. FTIR analysis indicated that ester bonds ruptured in the phantom during a 40 Gy radiation dosage, resembling alterations seen in breast tumor cell membranes after radiation exposure.</div></div><div><h3>Conclusion</h3><div>This phantom proves to be a valuable tool for evaluating cancer treatment strategies. The penetration of radiation in the breast cancer phantom will allow us to explore the effects of radiation on target cells. It will additionally help us in optimizing the radiation dose for breast cancer.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"230 ","pages":"Article 112556"},"PeriodicalIF":2.8,"publicationDate":"2025-01-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143072399","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Closed-loop method for accurate measurement of Rn-220 exhalation rate from soil surfaces
IF 2.8 3区 物理与天体物理 Q3 CHEMISTRY, PHYSICAL Pub Date : 2025-01-22 DOI: 10.1016/j.radphyschem.2025.112561
Xianfa Mao , Zhongkai Fan , Shuaibin Liu , Ruomei Xie , Shuai Yuan , Huiying Li , Jiale Sun , Jiulin Wu , Haibo Yi , Zhipeng Liu , Xinyue Yang , Shicheng Luo , Chenxi Zu , Feng Xiao , Hongbo Xu , Hongzhi Yuan , Yanliang Tan
Rn-220 is an important isotope of radon. The relatively short half-life of Rn-220 presents a significant challenge in accurately determining its exhalation rate. As the risk of exposure to Rn-220 continues to rise, the accurate measurement of Rn-220 and its exhalation rate has become a significant challenge in the field of radiation protection. Traditional model only considers the change of Rn-220 concentration in the accumulation chamber. The influence of outflow, inflow and decay of Rn-220 at the inlet and outlet of the accumulation chamber on the concentration of Rn-220 in the accumulation chamber is not considered. Therefore, the actual Rn-220 exhalation rate is difficult to accurately reflect. In this paper, a new Rn-220 exhalation model was proposed. Considering the change of Rn-220 concentration at the inlet and outlet of the accumulation chamber, the theoretical model was established between Rn-220 from the accumulation chamber to the inner chamber of RAD7 and back to the accumulation chamber. Verified through three sets of experiments, the model more accurately reflects the accumulation and decay process of Rn-220 in the closed-loop system, compared to the traditional model, the new model improves the measurement reliability from the theoretical perspective, with an enhancement of 16.15%. This new model offers a precise means of measuring Rn-220 exhalation rates from soil surfaces.
{"title":"Closed-loop method for accurate measurement of Rn-220 exhalation rate from soil surfaces","authors":"Xianfa Mao ,&nbsp;Zhongkai Fan ,&nbsp;Shuaibin Liu ,&nbsp;Ruomei Xie ,&nbsp;Shuai Yuan ,&nbsp;Huiying Li ,&nbsp;Jiale Sun ,&nbsp;Jiulin Wu ,&nbsp;Haibo Yi ,&nbsp;Zhipeng Liu ,&nbsp;Xinyue Yang ,&nbsp;Shicheng Luo ,&nbsp;Chenxi Zu ,&nbsp;Feng Xiao ,&nbsp;Hongbo Xu ,&nbsp;Hongzhi Yuan ,&nbsp;Yanliang Tan","doi":"10.1016/j.radphyschem.2025.112561","DOIUrl":"10.1016/j.radphyschem.2025.112561","url":null,"abstract":"<div><div>Rn-220 is an important isotope of radon. The relatively short half-life of Rn-220 presents a significant challenge in accurately determining its exhalation rate. As the risk of exposure to Rn-220 continues to rise, the accurate measurement of Rn-220 and its exhalation rate has become a significant challenge in the field of radiation protection. Traditional model only considers the change of Rn-220 concentration in the accumulation chamber. The influence of outflow, inflow and decay of Rn-220 at the inlet and outlet of the accumulation chamber on the concentration of Rn-220 in the accumulation chamber is not considered. Therefore, the actual Rn-220 exhalation rate is difficult to accurately reflect. In this paper, a new Rn-220 exhalation model was proposed. Considering the change of Rn-220 concentration at the inlet and outlet of the accumulation chamber, the theoretical model was established between Rn-220 from the accumulation chamber to the inner chamber of RAD7 and back to the accumulation chamber. Verified through three sets of experiments, the model more accurately reflects the accumulation and decay process of Rn-220 in the closed-loop system, compared to the traditional model, the new model improves the measurement reliability from the theoretical perspective, with an enhancement of 16.15%. This new model offers a precise means of measuring Rn-220 exhalation rates from soil surfaces.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"229 ","pages":"Article 112561"},"PeriodicalIF":2.8,"publicationDate":"2025-01-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143035263","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Comparative surface dosimetry in breast cancer in 3DCRT radiotherapy: TLD measurements and TPS evaluation across techniques
IF 2.9 3区 物理与天体物理 Q3 CHEMISTRY, PHYSICAL Pub Date : 2025-01-22 DOI: 10.1016/j.radphyschem.2025.112559
Saeid Afereydoon, Mohammad Javad Enferadi-Aliabad, Mahdie Gholizadeh, Yasaman Rezaei, Mohammad Ali Broomand, Reza Daneshfar, Abolfazl Nickfarjam
Breast cancer remains a leading global health issue for women, External Beam Radiotherapy is commonly used post-surgery but often causes acute skin reactions. Accurate calculating superficial doses remains difficult despite Treatment planning system (TPS) advancements, due to particle equilibrium complexities and near-surface modeling limitations. skin dose measurement is critical for effective treatment and minimizing side effects. This study aims to calculate skin doses in breast cancer patients using TLD chips and compare them with TPS-calculated doses. The comparison includes single and dual isocenter techniques for key region such as match-line, nipple, under the MLC, supraclavicular and out of field like in cardiac regions with two different machine COMPACT and ONCOR.
{"title":"Comparative surface dosimetry in breast cancer in 3DCRT radiotherapy: TLD measurements and TPS evaluation across techniques","authors":"Saeid Afereydoon, Mohammad Javad Enferadi-Aliabad, Mahdie Gholizadeh, Yasaman Rezaei, Mohammad Ali Broomand, Reza Daneshfar, Abolfazl Nickfarjam","doi":"10.1016/j.radphyschem.2025.112559","DOIUrl":"https://doi.org/10.1016/j.radphyschem.2025.112559","url":null,"abstract":"Breast cancer remains a leading global health issue for women, External Beam Radiotherapy is commonly used post-surgery but often causes acute skin reactions. Accurate calculating superficial doses remains difficult despite Treatment planning system (TPS) advancements, due to particle equilibrium complexities and near-surface modeling limitations. skin dose measurement is critical for effective treatment and minimizing side effects. This study aims to calculate skin doses in breast cancer patients using TLD chips and compare them with TPS-calculated doses. The comparison includes single and dual isocenter techniques for key region such as match-line, nipple, under the MLC, supraclavicular and out of field like in cardiac regions with two different machine COMPACT and ONCOR.","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"111 1","pages":""},"PeriodicalIF":2.9,"publicationDate":"2025-01-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143035265","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Enhancing austenitic stainless-steel alloys for fast breeder reactor fuel cladding: A comparative study
IF 2.8 3区 物理与天体物理 Q3 CHEMISTRY, PHYSICAL Pub Date : 2025-01-22 DOI: 10.1016/j.radphyschem.2025.112544
Sara E. Saleh , M.K. Elfawkhry , Heba A. Saudi , Hosam M. Gomaa , S.M. El-Minyawi , M.M. Eissa
In the present study, a series of austenitic stainless-steel alloys were developed for use as fuel cladding in fast breeder reactors. Standard austenitic stainless steel AISI316L was prepared and studied as a reference sample. Either intermetallic phases or secondary carbides were suggested to enhance the characteristic properties of austenitic stainless steel. Therefore, two samples were prepared by partially and completely replacing molybdenum with tungsten and a third sample was micro-alloyed with titanium. The characteristic properties of the three prepared alloys were compared with those of AISI316L through thermodynamic calculations that predicted the possible phases in the different alloys. Scanning electron microscopes detected the microstructure of the other alloys, and X-ray diffraction patterns of the new alloys were compared with the standard alloys. The mechanical properties of the prepared alloys were studied using Vickers hardness and tensile tests, which were conducted at room temperature to monitor the enhancement in the characteristic properties of the stainless-steel alloys. The results show that the modified austenitic stainless steel samples containing tungsten or titanium have preferable properties, such as higher hardness and yield strength. The nuclear properties of the modified stainless-steel alloys were measured using nine different gamma-ray energy lines to determine the mass attenuation coefficients (σ, cm2/g) for the alloy samples, and the results showed an excellent agreement with those calculated using the WinXcom computer program (Version 3.1). The macroscopic neutron cross-sections (Σ, cm⁻1) for the prepared stainless-steel alloys were measured using four types of neutron energies, which were affected in the modified stainless-steel alloys.
{"title":"Enhancing austenitic stainless-steel alloys for fast breeder reactor fuel cladding: A comparative study","authors":"Sara E. Saleh ,&nbsp;M.K. Elfawkhry ,&nbsp;Heba A. Saudi ,&nbsp;Hosam M. Gomaa ,&nbsp;S.M. El-Minyawi ,&nbsp;M.M. Eissa","doi":"10.1016/j.radphyschem.2025.112544","DOIUrl":"10.1016/j.radphyschem.2025.112544","url":null,"abstract":"<div><div>In the present study, a series of austenitic stainless-steel alloys were developed for use as fuel cladding in fast breeder reactors. Standard austenitic stainless steel AISI316L was prepared and studied as a reference sample. Either intermetallic phases or secondary carbides were suggested to enhance the characteristic properties of austenitic stainless steel. Therefore, two samples were prepared by partially and completely replacing molybdenum with tungsten and a third sample was micro-alloyed with titanium. The characteristic properties of the three prepared alloys were compared with those of AISI316L through thermodynamic calculations that predicted the possible phases in the different alloys. Scanning electron microscopes detected the microstructure of the other alloys, and X-ray diffraction patterns of the new alloys were compared with the standard alloys. The mechanical properties of the prepared alloys were studied using Vickers hardness and tensile tests, which were conducted at room temperature to monitor the enhancement in the characteristic properties of the stainless-steel alloys. The results show that the modified austenitic stainless steel samples containing tungsten or titanium have preferable properties, such as higher hardness and yield strength. The nuclear properties of the modified stainless-steel alloys were measured using nine different gamma-ray energy lines to determine the mass attenuation coefficients (σ, cm<sup>2</sup>/g) for the alloy samples, and the results showed an excellent agreement with those calculated using the WinXcom computer program (Version 3.1). The macroscopic neutron cross-sections (Σ, cm⁻<sup>1</sup>) for the prepared stainless-steel alloys were measured using four types of neutron energies, which were affected in the modified stainless-steel alloys.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"230 ","pages":"Article 112544"},"PeriodicalIF":2.8,"publicationDate":"2025-01-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143049750","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Effect of Bi2O3 on the optical and radiation shielding properties of borotellurite glasses irradiate at 59 keV photon energy
IF 2.9 3区 物理与天体物理 Q3 CHEMISTRY, PHYSICAL Pub Date : 2025-01-22 DOI: 10.1016/j.radphyschem.2025.112563
N.H. Alias, M.H.M. Zaid, K.A. Matori, Y.W. Fen, S.N. Nazrin, N. Effendy
The optical and radiation shielding properties of the newly formulated bismuth borotellurite, [Bi2O3]x[(TeO2)70(B2O3)30]100-x glass system with x = 0, 5, 10, 15, and 20 mol% irradiated at 59 keV photon energy have been investigated. X-ray diffraction analysis confirm the amorphous structure of the glasses. The density of the glass sample increase from 3.962 to 6.400 g/cm3 with the increase of Bi2O3 concentration. From the results, the molar volume and oxygen packing density revealing an anomaly trend for the sample at a concentration 10 mol% of Bi2O3. Besides, the FTIR spectra showed an increase in the formation of bridging oxygen (BO) species, specifically BO4 bond as the progress of Bi2O3 concentration. According to the optical results, the optical band gaps decreased from 2.53 to 1.75 eV, the refractive index increase from 2.54 to 2.85, molar refraction increase from 21.56 to 23.32 cm3/mol and metallization decrease from 0.36 to 0.30 as the concentration of Bi2O3 increased within the glass matrix. This reduction in optical band gap is attributed to the rising basicity and polarizability. The addition of higher concentrations of Bi2O3 enhances the radiation shielding effectiveness of the glasses, as evidenced by the increased mass attenuation coefficient, ranging from 1.086 to 1.506 and half-value layer values. The lowest half-value layer is achieved for the glass sample 10 mol% Bi2O3 with the density of 4.968 g/cm³, measuring 0.096 cm at 59 keV photon energy. This indicates superior shielding resistance at low radiation energy, minimizing the thickness requirements of the radiation instrument in the medical field.
{"title":"Effect of Bi2O3 on the optical and radiation shielding properties of borotellurite glasses irradiate at 59 keV photon energy","authors":"N.H. Alias, M.H.M. Zaid, K.A. Matori, Y.W. Fen, S.N. Nazrin, N. Effendy","doi":"10.1016/j.radphyschem.2025.112563","DOIUrl":"https://doi.org/10.1016/j.radphyschem.2025.112563","url":null,"abstract":"The optical and radiation shielding properties of the newly formulated bismuth borotellurite, [Bi<ce:inf loc=\"post\">2</ce:inf>O<ce:inf loc=\"post\">3</ce:inf>]<ce:inf loc=\"post\"><ce:italic>x</ce:italic></ce:inf>[(TeO<ce:inf loc=\"post\">2</ce:inf>)<ce:inf loc=\"post\">70</ce:inf>(B<ce:inf loc=\"post\">2</ce:inf>O<ce:inf loc=\"post\">3</ce:inf>)<ce:inf loc=\"post\">30</ce:inf>]<ce:inf loc=\"post\">100-<ce:italic>x</ce:italic></ce:inf> glass system with <ce:italic>x</ce:italic> = 0, 5, 10, 15, and 20 mol% irradiated at 59 keV photon energy have been investigated. X-ray diffraction analysis confirm the amorphous structure of the glasses. The density of the glass sample increase from 3.962 to 6.400 g/cm<ce:sup loc=\"post\">3</ce:sup> with the increase of Bi<ce:inf loc=\"post\">2</ce:inf>O<ce:inf loc=\"post\">3</ce:inf> concentration. From the results, the molar volume and oxygen packing density revealing an anomaly trend for the sample at a concentration 10 mol% of Bi<ce:inf loc=\"post\">2</ce:inf>O<ce:inf loc=\"post\">3</ce:inf>. Besides, the FTIR spectra showed an increase in the formation of bridging oxygen (BO) species, specifically BO<ce:inf loc=\"post\">4</ce:inf> bond as the progress of Bi<ce:inf loc=\"post\">2</ce:inf>O<ce:inf loc=\"post\">3</ce:inf> concentration. According to the optical results, the optical band gaps decreased from 2.53 to 1.75 eV, the refractive index increase from 2.54 to 2.85, molar refraction increase from 21.56 to 23.32 cm<ce:sup loc=\"post\">3</ce:sup>/mol and metallization decrease from 0.36 to 0.30 as the concentration of Bi<ce:inf loc=\"post\">2</ce:inf>O<ce:inf loc=\"post\">3</ce:inf> increased within the glass matrix. This reduction in optical band gap is attributed to the rising basicity and polarizability. The addition of higher concentrations of Bi<ce:inf loc=\"post\">2</ce:inf>O<ce:inf loc=\"post\">3</ce:inf> enhances the radiation shielding effectiveness of the glasses, as evidenced by the increased mass attenuation coefficient, ranging from 1.086 to 1.506 and half-value layer values. The lowest half-value layer is achieved for the glass sample 10 mol% Bi<ce:inf loc=\"post\">2</ce:inf>O<ce:inf loc=\"post\">3</ce:inf> with the density of 4.968 g/cm³, measuring 0.096 cm at 59 keV photon energy. This indicates superior shielding resistance at low radiation energy, minimizing the thickness requirements of the radiation instrument in the medical field.","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"28 1","pages":""},"PeriodicalIF":2.9,"publicationDate":"2025-01-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143035264","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Radiation-induced degradation of di-butyl phthalate plasticizer in aqueous solution: Performance, pathways and toxicity assessment
IF 2.9 3区 物理与天体物理 Q3 CHEMISTRY, PHYSICAL Pub Date : 2025-01-22 DOI: 10.1016/j.radphyschem.2025.112557
Qin Wen, Jianlong Wang
Di-butyl phthalate (DBP), a widely used plasticizer, is ubiquitous in aquatic environments due to the widespread application of plastics. Moreover, DBP is refractory and difficult to remove in biological wastewater treatment process. In this study, radiation-induced degradation of DBP was investigated. The results showed that when the initial DBP concentration was 5–15 mg/L, the DBP degradation efficiency was more than 72% at the absorbed dose of 0.1 kGy, and the degradation of DBP followed a first-order kinetic model. The quenching experiments suggested that ·OH, H∙, and eaq were all involved in the DBP degradation, and ·OH played a major role. The acidic condition (pH = 3.5) was more conducive to DBP degradation. The existence of inorganic anions (HPO42−, Cl, NO3, or CO32−) and organic compounds (humic acid, peptone, or d-glucose) inhibited DBP degradation. The addition of oxidants (Fe2+, H2O2, PDS, PMS, or Fe2+/H2O2) could promote DBP degradation. Thirteen intermediate products were identified by LC-MS and the possible pathways of DBP degradation were inferred. The toxicity of DBP and its intermediates were predicted by ECOSAR. Most of the intermediates were less toxic than DBP, indicating the effectiveness of radiation degradation of DBP in reducing its toxicity. This study revealed that radiation is a promising technology for the effective degradation of DBP in aqueous solution.
{"title":"Radiation-induced degradation of di-butyl phthalate plasticizer in aqueous solution: Performance, pathways and toxicity assessment","authors":"Qin Wen, Jianlong Wang","doi":"10.1016/j.radphyschem.2025.112557","DOIUrl":"https://doi.org/10.1016/j.radphyschem.2025.112557","url":null,"abstract":"Di-butyl phthalate (DBP), a widely used plasticizer, is ubiquitous in aquatic environments due to the widespread application of plastics. Moreover, DBP is refractory and difficult to remove in biological wastewater treatment process. In this study, radiation-induced degradation of DBP was investigated. The results showed that when the initial DBP concentration was 5–15 mg/L, the DBP degradation efficiency was more than 72% at the absorbed dose of 0.1 kGy, and the degradation of DBP followed a first-order kinetic model. The quenching experiments suggested that ·OH, H∙, and e<ce:inf loc=\"post\">aq</ce:inf><ce:sup loc=\"post\">−</ce:sup> were all involved in the DBP degradation, and ·OH played a major role. The acidic condition (pH = 3.5) was more conducive to DBP degradation. The existence of inorganic anions (HPO<ce:inf loc=\"post\">4</ce:inf><ce:sup loc=\"post\">2−</ce:sup>, Cl<ce:sup loc=\"post\">−</ce:sup>, NO<ce:inf loc=\"post\">3</ce:inf><ce:sup loc=\"post\">−</ce:sup>, or CO<ce:inf loc=\"post\">3</ce:inf><ce:sup loc=\"post\">2−</ce:sup>) and organic compounds (humic acid, peptone, or <ce:small-caps>d</ce:small-caps>-glucose) inhibited DBP degradation. The addition of oxidants (Fe<ce:sup loc=\"post\">2+</ce:sup>, H<ce:inf loc=\"post\">2</ce:inf>O<ce:inf loc=\"post\">2</ce:inf>, PDS, PMS, or Fe<ce:sup loc=\"post\">2+</ce:sup>/H<ce:inf loc=\"post\">2</ce:inf>O<ce:inf loc=\"post\">2</ce:inf>) could promote DBP degradation. Thirteen intermediate products were identified by LC-MS and the possible pathways of DBP degradation were inferred. The toxicity of DBP and its intermediates were predicted by ECOSAR. Most of the intermediates were less toxic than DBP, indicating the effectiveness of radiation degradation of DBP in reducing its toxicity. This study revealed that radiation is a promising technology for the effective degradation of DBP in aqueous solution.","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"35 1","pages":""},"PeriodicalIF":2.9,"publicationDate":"2025-01-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143035266","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Polymer-based shielding with micro- and nanoparticles: An investigation to reduce photon and photoneutron contamination in a LINAC treatment room
IF 2.9 3区 物理与天体物理 Q3 CHEMISTRY, PHYSICAL Pub Date : 2025-01-22 DOI: 10.1016/j.radphyschem.2025.112553
M. Dejangah, H. Sadeghi, N. Vosoughi, E. Asadi Amirabadi
The presence of photons and neutrons in the Linear Accelerator (LINAC) treatment room poses significant risks to both patients and staff. As a result, optimizing shielding materials to reduce photoneutron contamination has become a vital area of research. This study investigates the effectiveness of composite materials incorporating micro- and nanosized particles for shielding against photons and neutrons emitted by medical LINACs. The theoretical analysis was performed using the Monte Carlo N-Particle Transport Code (MCNP) version 6.1, employing two strategies to improve computational efficiency: firstly, replacing the photon source derived from emitted photons with a primary electron beam, and secondly, utilizing the Surface Source Write/Surface Source Read (SSW/SSR) cards. The phase space around the LINAC head was characterized and assessed at the isocenter both with and without shielding across 11 different materials. The impact of micro- and nanosized particles on the shielding's attenuation properties was analyzed, and the absorbed doses in a phantom were examined with and without microparticle fillers. Additionally, the composite matrix exhibited enhanced performance when combined with tungsten (W) and boron carbide fillers.
{"title":"Polymer-based shielding with micro- and nanoparticles: An investigation to reduce photon and photoneutron contamination in a LINAC treatment room","authors":"M. Dejangah, H. Sadeghi, N. Vosoughi, E. Asadi Amirabadi","doi":"10.1016/j.radphyschem.2025.112553","DOIUrl":"https://doi.org/10.1016/j.radphyschem.2025.112553","url":null,"abstract":"The presence of photons and neutrons in the Linear Accelerator (LINAC) treatment room poses significant risks to both patients and staff. As a result, optimizing shielding materials to reduce photoneutron contamination has become a vital area of research. This study investigates the effectiveness of composite materials incorporating micro- and nanosized particles for shielding against photons and neutrons emitted by medical LINACs. The theoretical analysis was performed using the Monte Carlo N-Particle Transport Code (MCNP) version 6.1, employing two strategies to improve computational efficiency: firstly, replacing the photon source derived from emitted photons with a primary electron beam, and secondly, utilizing the Surface Source Write/Surface Source Read (SSW/SSR) cards. The phase space around the LINAC head was characterized and assessed at the isocenter both with and without shielding across 11 different materials. The impact of micro- and nanosized particles on the shielding's attenuation properties was analyzed, and the absorbed doses in a phantom were examined with and without microparticle fillers. Additionally, the composite matrix exhibited enhanced performance when combined with tungsten (W) and boron carbide fillers.","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"1067 1","pages":""},"PeriodicalIF":2.9,"publicationDate":"2025-01-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143035269","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Non-invasive estimation of absorbed ionizing radiation dose in mice using near-infrared spectroscopy (NIRS) and aquaphotomics
IF 2.9 3区 物理与天体物理 Q3 CHEMISTRY, PHYSICAL Pub Date : 2025-01-21 DOI: 10.1016/j.radphyschem.2025.112554
Jelena Muncan, Masaru Yamaguchi, Ikuo Kashiwakura, Roumiana Tsenkova
Accurate measurement of ionizing radiation exposure, whether therapeutic or accidental, is of utmost importance in various scenarios. This paper presents a study that addresses this critical need by utilizing near-infrared (NIR) spectroscopy and aquaphotomics to estimate radiation dose exposure in mouse models subjected to X-ray irradiation. The analysis of NIR spectra acquired from the mouse abdomen enabled non-invasive estimation of radiation doses ranging from 0.5 to 6.5 Gy, immediately following the irradiation exposure. The findings were consistent with the impact of total body irradiation in mice, as evidenced by measures such as animal survival rate, alterations in body weight observed over a 30-day post-exposure period, and changes in hematocrit levels. The spectroscopic measurements were based on detecting changes in the molecular structure of body water after radiation exposure, utilizing the water spectral pattern as a multidimensional biomarker. While further validation in nonhuman primates is necessary, the findings demonstrate a simple, non-destructive, and rapid method that holds promise for the estimation of radiation exposure across a range of doses, applicable to both clinical applications and catastrophic radiation events. These advancements in radiation dose quantification have significant implications for the timely and precise assessment of radiation exposure in humans.
{"title":"Non-invasive estimation of absorbed ionizing radiation dose in mice using near-infrared spectroscopy (NIRS) and aquaphotomics","authors":"Jelena Muncan, Masaru Yamaguchi, Ikuo Kashiwakura, Roumiana Tsenkova","doi":"10.1016/j.radphyschem.2025.112554","DOIUrl":"https://doi.org/10.1016/j.radphyschem.2025.112554","url":null,"abstract":"Accurate measurement of ionizing radiation exposure, whether therapeutic or accidental, is of utmost importance in various scenarios. This paper presents a study that addresses this critical need by utilizing near-infrared (NIR) spectroscopy and aquaphotomics to estimate radiation dose exposure in mouse models subjected to X-ray irradiation. The analysis of NIR spectra acquired from the mouse abdomen enabled non-invasive estimation of radiation doses ranging from 0.5 to 6.5 Gy, immediately following the irradiation exposure. The findings were consistent with the impact of total body irradiation in mice, as evidenced by measures such as animal survival rate, alterations in body weight observed over a 30-day post-exposure period, and changes in hematocrit levels. The spectroscopic measurements were based on detecting changes in the molecular structure of body water after radiation exposure, utilizing the water spectral pattern as a multidimensional biomarker. While further validation in nonhuman primates is necessary, the findings demonstrate a simple, non-destructive, and rapid method that holds promise for the estimation of radiation exposure across a range of doses, applicable to both clinical applications and catastrophic radiation events. These advancements in radiation dose quantification have significant implications for the timely and precise assessment of radiation exposure in humans.","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"49 1","pages":""},"PeriodicalIF":2.9,"publicationDate":"2025-01-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143035267","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
期刊
Radiation Physics and Chemistry
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