Pub Date : 2026-06-01Epub Date: 2026-02-03DOI: 10.1016/j.radphyschem.2026.113646
Mehmet Bektasoglu , Abdullah S. Bayraktar
We introduce GRASP-X, a fast and user-friendly online tool for computing key gamma-ray shielding parameters, including the mass attenuation coefficient (MAC), half-value layer (HVL), tenth-value layer (TVL), mean free path (MFP), and effective atomic number (). GRASP-X is based on the previously developed offline version ”GRASP” and is freely accessible at https://nuclearandparticle.sakarya.edu.tr/grasp-x. The tool computes these parameters at both standard gamma-ray energies and absorption edges, producing graphical outputs and downloadable tables in approximately one second. To evaluate its performance, a wide range of previously studied materials — including glasses and composites — was analyzed. MACs, HVLs, and values obtained with GRASP-X were benchmarked against results from established computational tools, experimental measurements, and theoretical predictions. GRASP-X shows excellent agreement with XCOM across nearly the entire gamma-ray energy range, including absorption edges, and its MAC results are consistent with those calculated using simulation codes such as PHITS and MCNP6. Although direct comparison with Phy-X at absorption edges was limited by the absence of corresponding data, GRASP-X results agree well with Phy-X at standard energies. The effective atomic numbers computed by GRASP-X also exhibit strong consistency with those from Auto-, particularly within the Compton interaction regime.
{"title":"GRASP-X: A user-friendly web-based code to compute various gamma shielding parameters","authors":"Mehmet Bektasoglu , Abdullah S. Bayraktar","doi":"10.1016/j.radphyschem.2026.113646","DOIUrl":"10.1016/j.radphyschem.2026.113646","url":null,"abstract":"<div><div>We introduce GRASP-X, a fast and user-friendly online tool for computing key gamma-ray shielding parameters, including the mass attenuation coefficient (MAC), half-value layer (HVL), tenth-value layer (TVL), mean free path (MFP), and effective atomic number (<span><math><msub><mrow><mi>Z</mi></mrow><mrow><mi>eff</mi></mrow></msub></math></span>). GRASP-X is based on the previously developed offline version ”GRASP” and is freely accessible at <span><span>https://nuclearandparticle.sakarya.edu.tr/grasp-x</span><svg><path></path></svg></span>. The tool computes these parameters at both standard gamma-ray energies and absorption edges, producing graphical outputs and downloadable tables in approximately one second. To evaluate its performance, a wide range of previously studied materials — including glasses and composites — was analyzed. MACs, HVLs, and <span><math><msub><mrow><mi>Z</mi></mrow><mrow><mi>eff</mi></mrow></msub></math></span> values obtained with GRASP-X were benchmarked against results from established computational tools, experimental measurements, and theoretical predictions. GRASP-X shows excellent agreement with XCOM across nearly the entire gamma-ray energy range, including absorption edges, and its MAC results are consistent with those calculated using simulation codes such as PHITS and MCNP6. Although direct comparison with Phy-X at absorption edges was limited by the absence of corresponding data, GRASP-X results agree well with Phy-X at standard energies. The effective atomic numbers computed by GRASP-X also exhibit strong consistency with those from Auto-<span><math><msub><mrow><mi>Z</mi></mrow><mrow><mi>e</mi><mi>f</mi><mi>f</mi></mrow></msub></math></span>, particularly within the Compton interaction regime.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"243 ","pages":"Article 113646"},"PeriodicalIF":2.8,"publicationDate":"2026-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146110481","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}
Pub Date : 2026-06-01Epub Date: 2026-02-01DOI: 10.1016/j.radphyschem.2026.113686
Hector Rene Vega-Carrillo , Samah A. Al-Shelkamy , Claudia Angelica Marquez-Mata , Carina Oliva Torres-Cortes , Victor Martin Hernandez-Davila , Miguel Angel Salas-Luevano
Seven shape memory alloys, together with AISI 321 stainless steel and polyethylene, were investigated as moderators for a241Am–Be neutron source. Monte Carlo simulations were performed to estimate the neutron spectra at 100 cm from the source, with the aim of producing realistic neutron radiation fields comprising thermal, epithermal, and fast neutrons suitable for calibration of neutron radiation protection instruments. In addition, γ-ray spectra induced by neutron interactions with, the source, alloy, steel, and polyethylene nuclei were evaluated. Using the calculated neutron spectra, the ambient dose equivalent, isotropic effective dose, and ambient dose were determined, while the ambient dose equivalent and ambient dose were also calculated for the γ-ray spectra. The neutron spectra of alloy-moderated 241Am–Be sources, including configurations with thin and thick polyethylene shells, exhibited neutron absorption features associated with 55Mn present in all alloys. Neutron spectra produced by thin and thick alloy shell–polyethylene moderated 241Am–Be sources showed well-defined thermal, epithermal, and fast neutron components, with mean neutron energies ranging from 1.53 to 2.48 MeV. Among the investigated configurations, the thick ASH4P/241Am–Be source produced the highest neutron fluence, with a mean energy of approximately 2.16 MeV and a balanced contribution of thermal, epithermal, and fast neutrons. These results demonstrate that shape memory alloys, in combination with polyethylene, can be effectively used to tailor 241Am–Be neutron fields, enabling the generation of realistic spectral and dosimetric characteristics suitable for extending the calibration capabilities of neutron calibration facilities.
{"title":"Spectra and dosimetric features of Shape Memory Alloys moderated 241Am–Be neutron sources for calibration","authors":"Hector Rene Vega-Carrillo , Samah A. Al-Shelkamy , Claudia Angelica Marquez-Mata , Carina Oliva Torres-Cortes , Victor Martin Hernandez-Davila , Miguel Angel Salas-Luevano","doi":"10.1016/j.radphyschem.2026.113686","DOIUrl":"10.1016/j.radphyschem.2026.113686","url":null,"abstract":"<div><div>Seven shape memory alloys, together with AISI 321 stainless steel and polyethylene, were investigated as moderators for a<sup>241</sup>Am–Be neutron source. Monte Carlo simulations were performed to estimate the neutron spectra at 100 cm from the source, with the aim of producing realistic neutron radiation fields comprising thermal, epithermal, and fast neutrons suitable for calibration of neutron radiation protection instruments. In addition, γ-ray spectra induced by neutron interactions with, the source, alloy, steel, and polyethylene nuclei were evaluated. Using the calculated neutron spectra, the ambient dose equivalent, isotropic effective dose, and ambient dose were determined, while the ambient dose equivalent and ambient dose were also calculated for the γ-ray spectra. The neutron spectra of alloy-moderated <sup>241</sup>Am–Be sources, including configurations with thin and thick polyethylene shells, exhibited neutron absorption features associated with <sup>55</sup>Mn present in all alloys. Neutron spectra produced by thin and thick alloy shell–polyethylene moderated <sup>241</sup>Am–Be sources showed well-defined thermal, epithermal, and fast neutron components, with mean neutron energies ranging from 1.53 to 2.48 MeV. Among the investigated configurations, the thick A<sub>SH4</sub>P/<sup>241</sup>Am–Be source produced the highest neutron fluence, with a mean energy of approximately 2.16 MeV and a balanced contribution of thermal, epithermal, and fast neutrons. These results demonstrate that shape memory alloys, in combination with polyethylene, can be effectively used to tailor <sup>241</sup>Am–Be neutron fields, enabling the generation of realistic spectral and dosimetric characteristics suitable for extending the calibration capabilities of neutron calibration facilities.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"243 ","pages":"Article 113686"},"PeriodicalIF":2.8,"publicationDate":"2026-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146110485","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}
Pub Date : 2026-05-01Epub Date: 2026-01-06DOI: 10.1016/j.radphyschem.2026.113623
Haifa M. Almutairi
New synthetic composites were developed and composed of Diglycidyl ether of bisphenol A (DGBA) polymer as a matrix material and BaO-Nanoparticles (NPs) and ZrO2-Microparticles (MPs) as a filler oxide with different percentages. Four DGBA-composites were fabricated and namely DGBA-BZ1(55DGBA:33BaO:12ZrO2), DGBA-BZ2 (50:35:15), DGBA-BZ3 (45:37:18) to DGBA-BZ4 (40:40:20) in weight percentage. The density of DGBA-composites ranged from 1.927 to 2.352 g cm−3. The gamma-ray shielding capability of these composites was estimated experimentally using several gamma-sources and a germanium detector (HPGe), and theoretically using the Phy-X/PSD software. The two approaches showed good agreement, with a maximum difference of ±6 %. The linear attenuation coefficients (LAC) of DGBA-composites were 5.852, 6.704, 7.669 and 8.894 cm−1 at 0.060 MeV for DGBA-BZ1, DGBA-BZ2, DGBA-BZ3 and DGBA-BZ4, respectively. The LAC at 0.662 MeV was 0.153, 0.162, 0.173 and 0.185 cm−1. This indicates a decrease in shielding efficiency with increasing gamma radiation energy, due to the dominance of Compton scattering at higher photon energies. Furthermore, composites containing the highest concentrations of BaO-NPs and ZrO2-MPs achieve the highest attenuation and shielding efficiency, due to the increased density and atomic number of the composites. DGBA-BZ4 achieved RSE 60.3 % at 5 cm, comparable to commercial glass RS-253 glass 61.3 %. The study found that these composites can compete with eco-friendly shielding materials for low-energy ionizing photons.
{"title":"Gamma-rays shielding assessments for polyepoxide composites reinforced by BaO-NPs and ZrO2-MPs","authors":"Haifa M. Almutairi","doi":"10.1016/j.radphyschem.2026.113623","DOIUrl":"10.1016/j.radphyschem.2026.113623","url":null,"abstract":"<div><div>New synthetic composites were developed and composed of Diglycidyl ether of bisphenol A (DGBA) polymer as a matrix material and BaO-Nanoparticles (NPs) and ZrO<sub>2</sub>-Microparticles (MPs) as a filler oxide with different percentages. Four DGBA-composites were fabricated and namely DGBA-BZ1(55DGBA:33BaO:12ZrO<sub>2</sub>), DGBA-BZ2 (50:35:15), DGBA-BZ3 (45:37:18) to DGBA-BZ4 (40:40:20) in weight percentage. The density of DGBA-composites ranged from 1.927 to 2.352 g cm<sup>−3</sup>. The gamma-ray shielding capability of these composites was estimated experimentally using several gamma-sources and a germanium detector (HPGe), and theoretically using the Phy-X/PSD software. The two approaches showed good agreement, with a maximum difference of ±6 %. The linear attenuation coefficients (LAC) of DGBA-composites were 5.852, 6.704, 7.669 and 8.894 cm<sup>−1</sup> at 0.060 MeV for DGBA-BZ1, DGBA-BZ2, DGBA-BZ3 and DGBA-BZ4, respectively. The LAC at 0.662 MeV was 0.153, 0.162, 0.173 and 0.185 cm<sup>−1</sup>. This indicates a decrease in shielding efficiency with increasing gamma radiation energy, due to the dominance of Compton scattering at higher photon energies. Furthermore, composites containing the highest concentrations of BaO-NPs and ZrO<sub>2</sub>-MPs achieve the highest attenuation and shielding efficiency, due to the increased density and atomic number of the composites. DGBA-BZ4 achieved RSE 60.3 % at 5 cm, comparable to commercial glass RS-253 glass 61.3 %. The study found that these composites can compete with eco-friendly shielding materials for low-energy ionizing photons.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"242 ","pages":"Article 113623"},"PeriodicalIF":2.8,"publicationDate":"2026-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145926696","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}
Pub Date : 2026-05-01Epub Date: 2026-01-20DOI: 10.1016/j.radphyschem.2026.113653
D.A. Bradley , A. Basaif , A. Oresegun , H.T. Zubair , H.M. Zin , K.Y. Choo , S.A. Ibrahim , F. Moradi , M. Alkhorayef , Tingyu Wang , Jianxiang Wen , E. Lewis , H.A. Abdul-Rashid
Examination is made of the temporal pattern of 6–15 MeV electrons, specifically at the dose-rates familiar in use of conventional linacs. The observed intra-pulse sub-structure variations are a manifestation of linac power modifications (modulation occurring within the duration of a single accelerator pulse) and inter-bunch electron repulsion. The measurement system, focal in providing sub-μs temporal resolution as well as capability in covering the dose per pulse dynamic range, comprises an in-house fabricated Ge-doped fiber-sensor, a photon-counting circuit, a multi-pixel photon counter (MPPC), and a fast digital oscilloscope. Together with the observed pulse decay-time and magnitude of afterglow, the variations in intra-pulse sub-structure captured by the system can be expected to have influence upon the accuracy of dose deposition. The measurement capability of the optical fiber scintillator system is shown to be sufficient to serve present needs, largely negating a desire for more sophisticated systems offering superior temporal resolution.
{"title":"Intra-pulse sub-structure sensing of accelerated electrons","authors":"D.A. Bradley , A. Basaif , A. Oresegun , H.T. Zubair , H.M. Zin , K.Y. Choo , S.A. Ibrahim , F. Moradi , M. Alkhorayef , Tingyu Wang , Jianxiang Wen , E. Lewis , H.A. Abdul-Rashid","doi":"10.1016/j.radphyschem.2026.113653","DOIUrl":"10.1016/j.radphyschem.2026.113653","url":null,"abstract":"<div><div>Examination is made of the temporal pattern of 6–15 MeV electrons, specifically at the dose-rates familiar in use of conventional linacs. The observed intra-pulse sub-structure variations are a manifestation of linac power modifications (modulation occurring within the duration of a single accelerator pulse) and inter-bunch electron repulsion. The measurement system, focal in providing sub-μs temporal resolution as well as capability in covering the dose per pulse dynamic range, comprises an in-house fabricated Ge-doped fiber-sensor, a photon-counting circuit, a multi-pixel photon counter (MPPC), and a fast digital oscilloscope. Together with the observed pulse decay-time and magnitude of afterglow, the variations in intra-pulse sub-structure captured by the system can be expected to have influence upon the accuracy of dose deposition. The measurement capability of the optical fiber scintillator system is shown to be sufficient to serve present needs, largely negating a desire for more sophisticated systems offering superior temporal resolution.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"242 ","pages":"Article 113653"},"PeriodicalIF":2.8,"publicationDate":"2026-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146014452","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}
Pub Date : 2026-05-01Epub Date: 2026-01-20DOI: 10.1016/j.radphyschem.2026.113655
Longxing Zheng , Linchao Mei , Zhaojie Zhu , Yizhi Huang , Chaoyang Tu , G. Lakshminarayana , Qianqian Lin , Yan Wang
In response to the environmental concerns and limited stability of traditional scintillators for current-mode radiation detectors, which are often used in computed tomography, baggage screening, and non-destructive testing, this study used the Czochralski method to successfully grow YAG-based crystals doped with trivalent rare-earth ions, including Tb/Dy: YAG, Tb/Dy/Ce: YAG, and Tb/Dy/Lu: YAG crystals. Their X-ray scintillation properties and imaging performance were comprehensively investigated. The results reveal that Tb/Dy/Ce: YAG and Tb/Dy/Lu: YAG exhibit radioluminescence intensities exceeding those of commercial Ce: GAGG and Ce: LuAG crystals, demonstrating high sensitivity to X-ray irradiation. The minimum detectable doses for Tb/Dy/Ce: YAG and Tb/Dy/Lu: YAG were measured to be as low as 173.65 nGy s−1 and 211 nGy s−1, respectively—both significantly below the typical diagnostic dose of 5.5 μGy s−1. Moreover, these crystals exhibit excellent radiation stability. X-ray imaging tests further confirm that Tb/Dy/Ce: YAG and Tb/Dy/Lu: YAG offer high spatial resolution limits of 10.17 lp mm−1 and 19.4 lp mm−1, respectively, delivering high-quality imaging results. These findings underscore the superior scintillation performance of Tb/Dy/Ce: YAG and Tb/Dy/Lu: YAG crystals, and highlight their strong potential for advanced X-ray detection and imaging applications.
{"title":"Growth and scintillation performance of Tb/Dy: YAG, Tb/Dy/Lu: YAG and Tb/Dy/Ce: YAG crystals for X-ray imaging applications","authors":"Longxing Zheng , Linchao Mei , Zhaojie Zhu , Yizhi Huang , Chaoyang Tu , G. Lakshminarayana , Qianqian Lin , Yan Wang","doi":"10.1016/j.radphyschem.2026.113655","DOIUrl":"10.1016/j.radphyschem.2026.113655","url":null,"abstract":"<div><div>In response to the environmental concerns and limited stability of traditional scintillators for current-mode radiation detectors, which are often used in computed tomography, baggage screening, and non-destructive testing, this study used the Czochralski method to successfully grow YAG-based crystals doped with trivalent rare-earth ions, including Tb/Dy: YAG, Tb/Dy/Ce: YAG, and Tb/Dy/Lu: YAG crystals. Their X-ray scintillation properties and imaging performance were comprehensively investigated. The results reveal that Tb/Dy/Ce: YAG and Tb/Dy/Lu: YAG exhibit radioluminescence intensities exceeding those of commercial Ce: GAGG and Ce: LuAG crystals, demonstrating high sensitivity to X-ray irradiation. The minimum detectable doses for Tb/Dy/Ce: YAG and Tb/Dy/Lu: YAG were measured to be as low as 173.65 nGy s<sup>−1</sup> and 211 nGy s<sup>−1</sup>, respectively—both significantly below the typical diagnostic dose of 5.5 μGy s<sup>−1</sup>. Moreover, these crystals exhibit excellent radiation stability. X-ray imaging tests further confirm that Tb/Dy/Ce: YAG and Tb/Dy/Lu: YAG offer high spatial resolution limits of 10.17 lp mm<sup>−1</sup> and 19.4 lp mm<sup>−1</sup>, respectively, delivering high-quality imaging results. These findings underscore the superior scintillation performance of Tb/Dy/Ce: YAG and Tb/Dy/Lu: YAG crystals, and highlight their strong potential for advanced X-ray detection and imaging applications.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"242 ","pages":"Article 113655"},"PeriodicalIF":2.8,"publicationDate":"2026-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146014453","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}
Pub Date : 2026-05-01Epub Date: 2025-12-11DOI: 10.1016/j.radphyschem.2025.113565
Jiatong Li , Hao Wang , Yi Zhang , Pingkun Cai , Can Cheng , Lian Chen , Enkang Luo , Changlin Niu , Dehui Zhang , Jipeng Liu , Zhen Li , Wenbao Jia , Daqian Hei
In the research, a novel inversion method for reconstruction of the neutron flux distribution based on Prompt Gamma-ray Neutron Activation Analysis (PGNAA) technology was proposed. For validating the feasibility of the proposed method, a PGNAA set-up was built with the D-T neutron generator and BGO detector as the core components, and the pure water sample was set for measurement. Combined with the maximum likelihood expectation maximization (MLEM) algorithm, the neutron-induced characteristic gamma-rays of [email protected] MeV and [email protected] MeV, which generated from thermal neutron capture reaction and fast neutron inelastic scattering reaction, were used for calculating the thermal neutron distribution and fast neutron distribution, respectively. Through both simulated calculation and experimental measurement, the performance of neutron distribution calculation was investigated by using the different evaluated factors, including Structural SIMilarities (SSIM), Cosine SIMilarity (CSIM), and Root Mean Squared Error (RMSE). Since the SSIM values of the reconstructed images were almost greater than 0.65 under different neutron flux distribution conditions, the feasibility of the proposed method for reconstructing neutron flux distributions was verified.
{"title":"Research on the neutron flux distribution measurement method based on PGNAA technology","authors":"Jiatong Li , Hao Wang , Yi Zhang , Pingkun Cai , Can Cheng , Lian Chen , Enkang Luo , Changlin Niu , Dehui Zhang , Jipeng Liu , Zhen Li , Wenbao Jia , Daqian Hei","doi":"10.1016/j.radphyschem.2025.113565","DOIUrl":"10.1016/j.radphyschem.2025.113565","url":null,"abstract":"<div><div>In the research, a novel inversion method for reconstruction of the neutron flux distribution based on Prompt Gamma-ray Neutron Activation Analysis (PGNAA) technology was proposed. For validating the feasibility of the proposed method, a PGNAA set-up was built with the D-T neutron generator and BGO detector as the core components, and the pure water sample was set for measurement. Combined with the maximum likelihood expectation maximization (MLEM) algorithm, the neutron-induced characteristic gamma-rays of <span><span><span>[email protected]</span></span><svg><path></path></svg></span> MeV and <span><span><span>[email protected]</span></span><svg><path></path></svg></span> MeV, which generated from thermal neutron capture reaction and fast neutron inelastic scattering reaction, were used for calculating the thermal neutron distribution and fast neutron distribution, respectively. Through both simulated calculation and experimental measurement, the performance of neutron distribution calculation was investigated by using the different evaluated factors, including Structural SIMilarities (SSIM), Cosine SIMilarity (CSIM), and Root Mean Squared Error (RMSE). Since the SSIM values of the reconstructed images were almost greater than 0.65 under different neutron flux distribution conditions, the feasibility of the proposed method for reconstructing neutron flux distributions was verified.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"242 ","pages":"Article 113565"},"PeriodicalIF":2.8,"publicationDate":"2026-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145732306","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}
Pub Date : 2026-05-01Epub Date: 2025-12-22DOI: 10.1016/j.radphyschem.2025.113581
Libing Chu , Jianlong Wang
The enhancement of methane production during anaerobic digestion of sludge was explored by using ionizing radiation as a pretreatment method. Biochemical Methane Potential (BMP) tests indicated a significant increase in maximum methane potential, ranging from 149 to 173 mL/g VS, in sludge irradiated at 10–50 kGy, compared to 99 mL/g VS in untreated sludge. Ionizing radiation can enhance anaerobic digestion by accelerating the hydrolysis and acidification process, which in turn leads to a shift in the composition of methanogenic archaea. After BMP test, the abundance of dominant bacterial phyla, Firmicutes and Bacteroidetes increased to 48.6 % and 25.8 % in irradiated sludge and a more diverse archaeal community, including common genera such as Methanosarcina, Methanobacterium, and Methanomassiliicoccus, as well as unique ones like Methanospirillum and Methanothermobacter was displayed. Furthermore, ionizing irradiation has also demonstrated its potential in enhancing methane production from sludge containing antibiotics such as oxytetracycline, norfloxacin and sulfamethoxazole.
{"title":"Pretreatment of sludge by ionizing radiation for enhanced methane production in anaerobic digestion: Effect of antibiotics and variation in bacterial and archaeal community","authors":"Libing Chu , Jianlong Wang","doi":"10.1016/j.radphyschem.2025.113581","DOIUrl":"10.1016/j.radphyschem.2025.113581","url":null,"abstract":"<div><div>The enhancement of methane production during anaerobic digestion of sludge was explored by using ionizing radiation as a pretreatment method. Biochemical Methane Potential (BMP) tests indicated a significant increase in maximum methane potential, ranging from 149 to 173 mL/g VS, in sludge irradiated at 10–50 kGy, compared to 99 mL/g VS in untreated sludge. Ionizing radiation can enhance anaerobic digestion by accelerating the hydrolysis and acidification process, which in turn leads to a shift in the composition of methanogenic archaea. After BMP test, the abundance of dominant bacterial phyla, <em>Firmicutes</em> and <em>Bacteroidetes</em> increased to 48.6 % and 25.8 % in irradiated sludge and a more diverse archaeal community, including common genera such as <em>Methanosarcina</em>, <em>Methanobacterium</em>, and <em>Methanomassiliicoccus</em>, as well as unique ones like <em>Methanospirillum</em> and <em>Methanothermobacter</em> was displayed. Furthermore, ionizing irradiation has also demonstrated its potential in enhancing methane production from sludge containing antibiotics such as oxytetracycline, norfloxacin and sulfamethoxazole.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"242 ","pages":"Article 113581"},"PeriodicalIF":2.8,"publicationDate":"2026-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145822838","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}
Pub Date : 2026-05-01Epub Date: 2026-01-03DOI: 10.1016/j.radphyschem.2026.113605
Minghui Liu, Min Zhu, Yanru Ren, Xuehui Dai, Panhui Chen, Jingyun Zhao, Siyuan Wang
Metal-Oxide-Semiconductor Field-Effect Transistors (MOSFETs) deployed in high-radiation environments, such as nuclear power plants, aerospace equipment, and satellites, face a critical challenge from the synergistic effects of total ionizing dose (TID) and hot-carrier injection (HCI1). This review comprehensively summarizes recent advances in understanding the individual damage mechanisms of TID and HCI. More importantly, it focuses on their synergistic degradation—arising from the complex interplay between the two effects in MOSFETs. A key consensus is that their interaction is not a simple linear superposition but a complex, nonlinear accelerated failure process driven by coupled defect kinetics. This review critically evaluates the roles of mainstream characterization techniques (e.g., capacitance-voltage (C–V), charge pumping (CP)) in probing the generation, evolution, and interaction of defects during degradation. Additionally, the review identifies core challenges such as the breakdown of cross-scale correlations between atomic defects and system lifetime, and insufficient modeling capability for multi-stress coupling effects, etc. Finally, this review outlines promising future directions aligned with integrated paradigms: establishing a "digital twin" reliability platform for full-chain failure prediction, and promoting "endogenous reliability" at the design stage via defect engineering, etc. This review synthesizes the current understanding and outlines future pathways, thus providing a solid foundation for enhancing the reliability of electronic devices operating in high-radiation environments.
{"title":"Overview of hot-carrier and total ionizing dose degradation mechanisms in MOSFETs","authors":"Minghui Liu, Min Zhu, Yanru Ren, Xuehui Dai, Panhui Chen, Jingyun Zhao, Siyuan Wang","doi":"10.1016/j.radphyschem.2026.113605","DOIUrl":"10.1016/j.radphyschem.2026.113605","url":null,"abstract":"<div><div>Metal-Oxide-Semiconductor Field-Effect Transistors (MOSFETs) deployed in high-radiation environments, such as nuclear power plants, aerospace equipment, and satellites, face a critical challenge from the synergistic effects of total ionizing dose (TID) and hot-carrier injection (HCI<span><span><sup>1</sup></span></span>). This review comprehensively summarizes recent advances in understanding the individual damage mechanisms of TID and HCI. More importantly, it focuses on their synergistic degradation—arising from the complex interplay between the two effects in MOSFETs. A key consensus is that their interaction is not a simple linear superposition but a complex, nonlinear accelerated failure process driven by coupled defect kinetics. This review critically evaluates the roles of mainstream characterization techniques (e.g., capacitance-voltage (C–V), charge pumping (CP)) in probing the generation, evolution, and interaction of defects during degradation. Additionally, the review identifies core challenges such as the breakdown of cross-scale correlations between atomic defects and system lifetime, and insufficient modeling capability for multi-stress coupling effects, etc. Finally, this review outlines promising future directions aligned with integrated paradigms: establishing a \"digital twin\" reliability platform for full-chain failure prediction, and promoting \"endogenous reliability\" at the design stage via defect engineering, etc. This review synthesizes the current understanding and outlines future pathways, thus providing a solid foundation for enhancing the reliability of electronic devices operating in high-radiation environments.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"242 ","pages":"Article 113605"},"PeriodicalIF":2.8,"publicationDate":"2026-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145894082","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}
Pub Date : 2026-05-01Epub Date: 2026-01-02DOI: 10.1016/j.radphyschem.2026.113591
Osiris Núñez-Chongo , Mauricio Suárez-Durán , Hernán Asorey , Iván Sidelnik , Roberto Mendez , Manuel Carretero , Rafael Mayo-García , Antonio Juan Rubio-Montero , Angelines Alberto Morillas
Reliable neutron flux characterization and dosimetry are critical to the design, licensing, and safe operation of nuclear facilities. However, obtaining these quantities from as-built geometries usually involves translating computer-aided design (CAD) models into radiation-transport inputs. This is a fragmented process that lacks an end-to-end, auditable pipeline. Widely used tools address transport, but not the seamless integration of CAD-to-dose, and often require restrictive licences. We present NEREIDA: a modular, scalable framework that automates the process of creating high-resolution, three-dimensional neutron dose maps from native CAD models. NEREIDA unifies aspects such as geometry voxelization and activation analysis in common structural materials, producing dose equivalents and across complex facilities. The NEREIDA framework integrates Geant4 with external components to support realistic sources, phantoms, and background fields. Validation against 252Cf and 241Am-Be reference spectra demonstrates spectrometric accuracy, and large-scale benchmarks on CAD-derived geometries show near-linear scaling up to voxels and 15 000 particles per run. This scalability enables precise, facility-specific radiation assessments within a single, reproducible toolchain for design iteration, licensing, and routine safety in fast-neutron environments.
{"title":"NEREIDA: A computational framework for the design and dosimetric characterization of fast-neutron facilities","authors":"Osiris Núñez-Chongo , Mauricio Suárez-Durán , Hernán Asorey , Iván Sidelnik , Roberto Mendez , Manuel Carretero , Rafael Mayo-García , Antonio Juan Rubio-Montero , Angelines Alberto Morillas","doi":"10.1016/j.radphyschem.2026.113591","DOIUrl":"10.1016/j.radphyschem.2026.113591","url":null,"abstract":"<div><div>Reliable neutron flux characterization and dosimetry are critical to the design, licensing, and safe operation of nuclear facilities. However, obtaining these quantities from as-built geometries usually involves translating computer-aided design (CAD) models into radiation-transport inputs. This is a fragmented process that lacks an end-to-end, auditable pipeline. Widely used tools address transport, but not the seamless integration of CAD-to-dose, and often require restrictive licences. We present NEREIDA: a modular, scalable framework that automates the process of creating high-resolution, three-dimensional neutron dose maps from native CAD models. NEREIDA unifies aspects such as geometry voxelization and activation analysis in common structural materials, producing dose equivalents <span><math><mrow><msup><mrow><mi>H</mi></mrow><mrow><mo>∗</mo></mrow></msup><mrow><mo>(</mo><mn>10</mn><mo>)</mo></mrow></mrow></math></span> and <span><math><mrow><msub><mrow><mi>H</mi></mrow><mrow><mi>p</mi></mrow></msub><mrow><mo>(</mo><mn>10</mn><mo>)</mo></mrow></mrow></math></span> across complex facilities. The NEREIDA framework integrates Geant4 with external components to support realistic sources, phantoms, and background fields. Validation against <sup>252</sup>Cf and <sup>241</sup>Am-Be reference spectra demonstrates spectrometric accuracy, and large-scale benchmarks on CAD-derived geometries show near-linear scaling up to <span><math><mrow><mn>800</mn><msup><mrow><mn>0</mn></mrow><mrow><mn>3</mn></mrow></msup></mrow></math></span> voxels and 15<!--> <!-->000 particles per run. This scalability enables precise, facility-specific radiation assessments within a single, reproducible toolchain for design iteration, licensing, and routine safety in fast-neutron environments.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"242 ","pages":"Article 113591"},"PeriodicalIF":2.8,"publicationDate":"2026-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145894086","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}
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