Pub Date : 2026-02-07DOI: 10.1016/j.radphyschem.2026.113674
Anoud Saud Alshammari , U. Rilwan , Feras Alafer , Marwan F.S.H. AL-Kamali , Aml Almutery , Atef El-Taher
This study employed Phy-X software to investigate the radiation protection efficacy of different bricks fabricated from a mixture of clay, CaO (calcium oxide), Al2O3 (aluminum oxide), and Fe2O3 (iron oxide). As the oxide additives substituted clay, an increased in the density of the fabricated samples was noticed, with CL5Fe showcasing the superior value of 2.40 g/cm3. An improved linear attenuation coefficient (LAC) was also noticed, with CL5Fe demonstrating the greatest LAC value of 0.154 cm−1 at 0.6 MeV, which could be associated to its superior density due to presence of Fe2O3. The 0.6 MeV energy was chosen as a representative 137Cs value within the Compton-dominant region. Shielding performance was further evaluated from 0.0459 to 1.46 MeV, covering photoelectric-to-Compton-dominated interactions. CL5Fe also outsmarted other samples in terms of thermal stability and structural integrity, making it the best choice for gamma radiation protection. Future studies should evaluate shielding performance across 1.47–15 MeV to assess material suitability for medical imaging, radiotherapy, and nuclear radiation environments.
{"title":"A comparative analysis of radiation shielding character in engineered bricks blended with CaO, Al2O3, and Fe2O3 additives: thermal stability and Phy-X simulation insights into attenuation characteristics","authors":"Anoud Saud Alshammari , U. Rilwan , Feras Alafer , Marwan F.S.H. AL-Kamali , Aml Almutery , Atef El-Taher","doi":"10.1016/j.radphyschem.2026.113674","DOIUrl":"10.1016/j.radphyschem.2026.113674","url":null,"abstract":"<div><div>This study employed Phy-X software to investigate the radiation protection efficacy of different bricks fabricated from a mixture of clay, CaO (calcium oxide), Al<sub>2</sub>O<sub>3</sub> (aluminum oxide), and Fe<sub>2</sub>O<sub>3</sub> (iron oxide). As the oxide additives substituted clay, an increased in the density of the fabricated samples was noticed, with <strong>CL5Fe</strong> showcasing the superior value of 2.40 g/cm<sup>3</sup>. An improved linear attenuation coefficient (LAC) was also noticed, with <strong>CL5Fe</strong> demonstrating the greatest LAC value of 0.154 cm<sup>−1</sup> at 0.6 MeV, which could be associated to its superior density due to presence of Fe<sub>2</sub>O<sub>3</sub>. The 0.6 MeV energy was chosen as a representative 137Cs value within the Compton-dominant region. Shielding performance was further evaluated from 0.0459 to 1.46 MeV, covering photoelectric-to-Compton-dominated interactions. <strong>CL5Fe</strong> also outsmarted other samples in terms of thermal stability and structural integrity, making it the best choice for gamma radiation protection. Future studies should evaluate shielding performance across 1.47–15 MeV to assess material suitability for medical imaging, radiotherapy, and nuclear radiation environments.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"243 ","pages":"Article 113674"},"PeriodicalIF":2.8,"publicationDate":"2026-02-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146134647","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}
Szaibelyite ore has been demonstrated as a cost-effective filler with excellent thermal neutron shielding properties, and the resulting Szaibelyite ore-based epoxy composites exhibit performance superior to some high-end commercial materials. However, the hazards associated with secondary radiation emitted from interactions between thermal neutrons and elements such as boron and hydrogen during the shielding process remain inadequately studied. This paper integrates experimental measurements, computational simulations, and radiation protection theory to systematically investigate the gamma rays shielding performance, attenuation mechanisms, and relevant shielding parameters (for both narrow and broad beams) of Szaibelyite ore-based epoxy composites within the 0.015–15 MeV energy range. The results indicate that while the gamma rays shielding capacity of the composites enhances with increasing Szaibelyite ore content, while HVLγ of composites SE1−SE5 are between 6.5119 and 8.5366 cm, which is relatively low compared to ordinary concrete, and the protection against secondary radiation must be seriously addressed. Interpretation of the attenuation mechanisms based on elemental composition reveals that the shielding effectiveness is primarily determined by the predominant elements in the composites. Given that magnesium (Mg) is the element with the highest atomic number in the system, the fundamental reason for the weak gamma rays attenuation lies in the lack of high-atomic-number elements with strong shielding capabilities. This study provides a theoretical foundation and data support for the transformation of Szaibelyite ore into high-value shielding materials, contributing not only to the high-value utilization of boron resources and the sustainable development of the boron industry but also offering a new alternative pathway for developing low-cost, high-performance shielding materials.
{"title":"Unveiling the gamma rays attenuation mechanism in Szaibelyite ore-based shielding composites: The limiting role of low atomic number elements","authors":"Mengge Dong , Suying Zhou , Haofei Zhou , G. Lakshminarayana , M.I. Sayyed , Xiangxin Xue","doi":"10.1016/j.radphyschem.2026.113692","DOIUrl":"10.1016/j.radphyschem.2026.113692","url":null,"abstract":"<div><div>Szaibelyite ore has been demonstrated as a cost-effective filler with excellent thermal neutron shielding properties, and the resulting Szaibelyite ore-based epoxy composites exhibit performance superior to some high-end commercial materials. However, the hazards associated with secondary radiation emitted from interactions between thermal neutrons and elements such as boron and hydrogen during the shielding process remain inadequately studied. This paper integrates experimental measurements, computational simulations, and radiation protection theory to systematically investigate the gamma rays shielding performance, attenuation mechanisms, and relevant shielding parameters (for both narrow and broad beams) of Szaibelyite ore-based epoxy composites within the 0.015–15 MeV energy range. The results indicate that while the gamma rays shielding capacity of the composites enhances with increasing Szaibelyite ore content, while <em>HVL</em><sub>γ</sub> of composites SE1−SE5 are between 6.5119 and 8.5366 cm, which is relatively low compared to ordinary concrete, and the protection against secondary radiation must be seriously addressed. Interpretation of the attenuation mechanisms based on elemental composition reveals that the shielding effectiveness is primarily determined by the predominant elements in the composites. Given that magnesium (Mg) is the element with the highest atomic number in the system, the fundamental reason for the weak gamma rays attenuation lies in the lack of high-atomic-number elements with strong shielding capabilities. This study provides a theoretical foundation and data support for the transformation of Szaibelyite ore into high-value shielding materials, contributing not only to the high-value utilization of boron resources and the sustainable development of the boron industry but also offering a new alternative pathway for developing low-cost, high-performance shielding materials.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"243 ","pages":"Article 113692"},"PeriodicalIF":2.8,"publicationDate":"2026-02-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146134646","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}
The world produces large quantities of raw materials from agriculture, aquaculture, forestry, and livestock. However, there are estimated losses of up to 50% of raw materials throughout the harvesting, slaughtering, transportation, processing, storage, and consumption stages. Due to its composition, agro-industrial waste may be slower to degradable, resulting in accumulation and negative environmental impact. Despite this, these residues retain considerable concentrations of important bioactive compounds that could be reincorporated into new formulations. Because of this, it is essential to identify applications to convert these wastes into high-value-added products. In this context, ionizing radiation has stood out as a promising technique among the current resources available for reusing waste and reducing microbial load, as it is a clean technology, does not generate additional waste, and does not raise the temperature during processing, the main limitation of conventional methods. With ionizing radiation, a new proposal for waste management emerges to reincorporate it into new products, reducing waste and reducing environmental impact. Thus, this review summarizes the most recent research on the application of nuclear energy as a viable solution and technological innovation for reusing agro-industrial waste, addressing its positive and negative effects on nutritional preservation and availability of bioactive compounds. In addition, it provides a brief analysis of the acceptability of this technology and the dissemination of information about the benefits of this process in food and waste.
{"title":"Application of ionizing radiation technology in agro-industrial waste: A review","authors":"J.P.A.A. Barros , V. Spagnol , L.M. Rondan-Flores , B.G. Negrão , V.F. Benedetti , A.L.C.H. Villavicencio","doi":"10.1016/j.radphyschem.2026.113690","DOIUrl":"10.1016/j.radphyschem.2026.113690","url":null,"abstract":"<div><div>The world produces large quantities of raw materials from agriculture, aquaculture, forestry, and livestock. However, there are estimated losses of up to 50% of raw materials throughout the harvesting, slaughtering, transportation, processing, storage, and consumption stages. Due to its composition, agro-industrial waste may be slower to degradable, resulting in accumulation and negative environmental impact. Despite this, these residues retain considerable concentrations of important bioactive compounds that could be reincorporated into new formulations. Because of this, it is essential to identify applications to convert these wastes into high-value-added products. In this context, ionizing radiation has stood out as a promising technique among the current resources available for reusing waste and reducing microbial load, as it is a clean technology, does not generate additional waste, and does not raise the temperature during processing, the main limitation of conventional methods. With ionizing radiation, a new proposal for waste management emerges to reincorporate it into new products, reducing waste and reducing environmental impact. Thus, this review summarizes the most recent research on the application of nuclear energy as a viable solution and technological innovation for reusing agro-industrial waste, addressing its positive and negative effects on nutritional preservation and availability of bioactive compounds. In addition, it provides a brief analysis of the acceptability of this technology and the dissemination of information about the benefits of this process in food and waste.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"243 ","pages":"Article 113690"},"PeriodicalIF":2.8,"publicationDate":"2026-02-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146134650","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 : 2026-02-06DOI: 10.1016/j.radphyschem.2026.113699
Samar , N. Amjed , A. Naz , A.M. Wajid
An evaluation of production cross sections for the medically and industrially important cobalt radionuclides, namely, 58mCo, 57Co, and 56Co, was performed. Experimental data from literature were compiled and critically analyzed in comparison with theoretical results of three nuclear model codes TALYS-1.9, EMPIRE-3.2, and ALICE-IPPE. A theory-aided evaluation methodology was used to generate the recommended Cross sections for each production route and their corresponding impurities. Using these recommended datasets, thick target yields were calculated for all investigated production routes with their impurities. The best production routes were suggested with optimum energy ranges for high-purity production of 58mCo, 57Co, and 56Co radionuclides. In particular, the 55Mn(α,n)58mCo (13 → 7 MeV), 57Fe(p,n)57Co (15 → 6 MeV), and 56Fe(p,n)56Co (16 → 8 MeV) reactions were found to be the most favorable for reliable cyclotron production.
{"title":"Optimization of the cross section data for the cyclotron production of 56Co, 57Co, and 58mCo radionuclides","authors":"Samar , N. Amjed , A. Naz , A.M. Wajid","doi":"10.1016/j.radphyschem.2026.113699","DOIUrl":"10.1016/j.radphyschem.2026.113699","url":null,"abstract":"<div><div>An evaluation of production cross sections for the medically and industrially important cobalt radionuclides, namely, <sup>58m</sup>Co, <sup>57</sup>Co, and <sup>56</sup>Co, was performed. Experimental data from literature were compiled and critically analyzed in comparison with theoretical results of three nuclear model codes TALYS-1.9, EMPIRE-3.2, and ALICE-IPPE. A theory-aided evaluation methodology was used to generate the recommended Cross sections for each production route and their corresponding impurities. Using these recommended datasets, thick target yields were calculated for all investigated production routes with their impurities. The best production routes were suggested with optimum energy ranges for high-purity production of <sup>58m</sup>Co, <sup>57</sup>Co, and <sup>56</sup>Co radionuclides. In particular, the <sup>55</sup>Mn(α,n)<sup>58m</sup>Co (13 → 7 MeV), <sup>57</sup>Fe(p,n)<sup>57</sup>Co (15 → 6 MeV), and <sup>56</sup>Fe(p,n)<sup>56</sup>Co (16 → 8 MeV) reactions were found to be the most favorable for reliable cyclotron production.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"243 ","pages":"Article 113699"},"PeriodicalIF":2.8,"publicationDate":"2026-02-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146134648","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 : 2026-02-06DOI: 10.1016/j.radphyschem.2026.113694
Nikita Medvedev
Response of refractory high-entropy alloys MoNbTaVW and HfNbTaTiZr to ultrafast laser radiation is modelled with the hybrid code XTANT-3, combining tight-binding molecular dynamics with the transport Monte Carlo and Boltzmann equation. A two-temperature state with elevated electronic temperature and a cold atomic lattice is studied. The parameters of the electronic system in such a state are evaluated: electronic heat capacity, thermal conductivity, and electron-phonon coupling parameter with the electronic temperatures up to ∼25,000 K. It is also demonstrated that the two refractory alloys do not show signs of nonthermal melting up to the deposited doses of ∼10 eV/atom, making them more radiation resistant than the Cantor alloy or stainless steel. These results suggest that heavy-element high-entropy alloys are more radiation resistant than those containing only lighter elements. Damage in irradiated HfNbTaTiZr starts with the selective diffusion of Ti atoms, forming a transient superionic-like state.
{"title":"Resistance of refractory high-entropy alloys to ultrafast laser irradiation","authors":"Nikita Medvedev","doi":"10.1016/j.radphyschem.2026.113694","DOIUrl":"10.1016/j.radphyschem.2026.113694","url":null,"abstract":"<div><div>Response of refractory high-entropy alloys MoNbTaVW and HfNbTaTiZr to ultrafast laser radiation is modelled with the hybrid code XTANT-3, combining tight-binding molecular dynamics with the transport Monte Carlo and Boltzmann equation. A two-temperature state with elevated electronic temperature and a cold atomic lattice is studied. The parameters of the electronic system in such a state are evaluated: electronic heat capacity, thermal conductivity, and electron-phonon coupling parameter with the electronic temperatures up to ∼25,000 K. It is also demonstrated that the two refractory alloys do not show signs of nonthermal melting up to the deposited doses of ∼10 eV/atom, making them more radiation resistant than the Cantor alloy or stainless steel. These results suggest that heavy-element high-entropy alloys are more radiation resistant than those containing only lighter elements. Damage in irradiated HfNbTaTiZr starts with the selective diffusion of Ti atoms, forming a transient superionic-like state.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"243 ","pages":"Article 113694"},"PeriodicalIF":2.8,"publicationDate":"2026-02-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146134645","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 : 2026-02-06DOI: 10.1016/j.radphyschem.2026.113693
A. Khallouqi , H. Sekkat , O. Elmouden , N. Ghosne , I. Lagrini , A. Halimi , O. El rhazouani
Accurate dosimetry is crucial for optimizing radiotherapy outcomes, balancing tumor control with healthy tissue sparing. Water phantoms represent the gold standard due to their tissue-equivalent properties, yet practical limitations such as setup complexity and portability drive the need for solid alternatives. This study employs Monte Carlo simulations using the GATE platform to comprehensively evaluate the dosimetric equivalence of common solid phantoms; RW3, Nylon, PMMA, Polyester, Polyethylene, Polystyrene, Original Plastic Water, and Virtual Water; against water for a 6 MV flattened photon beam from a Varian TrueBeam linear accelerator. Dosimetric parameters, including percentage depth dose (PDD) curves, lateral dose profiles at depth of 10 cm, and 3D volumetric dose distributions, were assessed under identical beam configurations (10 × 10 cm2 field size, 100 cm SSD). Validation against experimental data acquired using a PTW Semiflex ionization chamber (0.125 cm3) in a motorized water phantom confirmed simulation fidelity, with gamma pass rates exceeding 99% (2%/2 mm criterion). Results ranked RW3 as the superior water substitute (mean PDD deviation: 0.65%; lateral: 4.68%; RMSE: 5.62%), followed by Plastic and Virtual phantoms, while Nylon, and Polyester exhibited unacceptable deviations (>10%). Polyethylene showed anomalous positive bias (+3.98% PDD). These findings, benchmarked against IAEA and AAPM tolerance criteria (±2% for reference dosimetry, ±3% for routine QA), highlight material-specific radiological properties influencing photon interactions, underscoring RW3's utility for clinical quality assurance while identifying materials requiring correction factors (Polystyrene, Polyethylene) or unsuitable for clinical use without extensive adjustments (Nylon, Polyester exceeding 10% deviation).
{"title":"Monte Carlo-based assessment of solid phantom equivalence to water in radiation therapy quality assurance","authors":"A. Khallouqi , H. Sekkat , O. Elmouden , N. Ghosne , I. Lagrini , A. Halimi , O. El rhazouani","doi":"10.1016/j.radphyschem.2026.113693","DOIUrl":"10.1016/j.radphyschem.2026.113693","url":null,"abstract":"<div><div>Accurate dosimetry is crucial for optimizing radiotherapy outcomes, balancing tumor control with healthy tissue sparing. Water phantoms represent the gold standard due to their tissue-equivalent properties, yet practical limitations such as setup complexity and portability drive the need for solid alternatives. This study employs Monte Carlo simulations using the GATE platform to comprehensively evaluate the dosimetric equivalence of common solid phantoms; RW3, Nylon, PMMA, Polyester, Polyethylene, Polystyrene, Original Plastic Water, and Virtual Water; against water for a 6 MV flattened photon beam from a Varian TrueBeam linear accelerator. Dosimetric parameters, including percentage depth dose (PDD) curves, lateral dose profiles at depth of 10 cm, and 3D volumetric dose distributions, were assessed under identical beam configurations (10 × 10 cm<sup>2</sup> field size, 100 cm SSD). Validation against experimental data acquired using a PTW Semiflex ionization chamber (0.125 cm<sup>3</sup>) in a motorized water phantom confirmed simulation fidelity, with gamma pass rates exceeding 99% (2%/2 mm criterion). Results ranked RW3 as the superior water substitute (mean PDD deviation: 0.65%; lateral: 4.68%; RMSE: 5.62%), followed by Plastic and Virtual phantoms, while Nylon, and Polyester exhibited unacceptable deviations (>10%). Polyethylene showed anomalous positive bias (+3.98% PDD). These findings, benchmarked against IAEA and AAPM tolerance criteria (±2% for reference dosimetry, ±3% for routine QA), highlight material-specific radiological properties influencing photon interactions, underscoring RW3's utility for clinical quality assurance while identifying materials requiring correction factors (Polystyrene, Polyethylene) or unsuitable for clinical use without extensive adjustments (Nylon, Polyester exceeding 10% deviation).</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"243 ","pages":"Article 113693"},"PeriodicalIF":2.8,"publicationDate":"2026-02-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146134652","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 : 2026-02-06DOI: 10.1016/j.radphyschem.2026.113697
K. Venkataramaniah, C. Scheidenberger, K. Vijay Sai, Deepa Seetharaman
{"title":"On the Precision and Accuracy of Audi-Wapstra-Wang Extrapolations for Nuclear Mass Predictions","authors":"K. Venkataramaniah, C. Scheidenberger, K. Vijay Sai, Deepa Seetharaman","doi":"10.1016/j.radphyschem.2026.113697","DOIUrl":"https://doi.org/10.1016/j.radphyschem.2026.113697","url":null,"abstract":"","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"77 1","pages":""},"PeriodicalIF":2.9,"publicationDate":"2026-02-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146134653","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 : 2026-02-05DOI: 10.1016/j.radphyschem.2026.113691
Sarah Sanaei Nasab , Neda Mollakhalili-Meybodi , Masoumeh Arab , Seyede Marzieh Hosseini , Hossein Fallahzadeh
Quinoa seeds were irradiated at doses of 0.5, 1, 2.5, 5, 7.5, and 10 kGy and then their technological characteristics were analyzed as physicochemical, functional, rheological, thermal, pasting, textural, FTIR, and morphological parameters.
Results indicated that gamma irradiation affected the glycosidic linkage of starch, the amylose/amylopectin ratio, and the tertiary structure of proteins, depending on dose. WHC (1.88 ± 0.01%), OHC (1.76 ± 0.01%), and WSI (4.09 ± 0.02 g/g) increased at 10 kGy, compared with the control, verified the enhanced hydrolytic depolymerization of starch. Significant decrease in the viscosity parameters (peak, hold, final, and setback), G’ and G”, and significant increase in tan δ (1.37 × 10−1±0.02 to 2.43 × 10−1±0.05) was observed. The lowest gelatination temperatures (onset, peak, conclusion) and enthalpy change of gelatinization were observed in sample irradiated at 10 kGy, which was attributed to the highest damage in starch structure induced by gamma irradiation. A decrease in hardness with increasing doses of gamma irradiation indicated increased crystallization of amylopectin. The analysis of FTIR confirmed the effects of gamma irradiation on carbohydrate and water absorption capacity, showing a reduction in O–H stretching vibrations and increases in C–H stretching and CO stretch, especially at 10 kGy. Scanning electron microscopy showed surface cracks and weakening of starch granules at 7.5 and 10 kGy. These results confirmed that higher doses affected technological properties and may be useful in food formulation.
{"title":"Effect of gamma irradiation treatment on the technological characteristics of quinoa flour","authors":"Sarah Sanaei Nasab , Neda Mollakhalili-Meybodi , Masoumeh Arab , Seyede Marzieh Hosseini , Hossein Fallahzadeh","doi":"10.1016/j.radphyschem.2026.113691","DOIUrl":"10.1016/j.radphyschem.2026.113691","url":null,"abstract":"<div><div>Quinoa seeds were irradiated at doses of 0.5, 1, 2.5, 5, 7.5, and 10 kGy and then their technological characteristics were analyzed as physicochemical, functional, rheological, thermal, pasting, textural, FTIR, and morphological parameters.</div><div>Results indicated that gamma irradiation affected the glycosidic linkage of starch, the amylose/amylopectin ratio, and the tertiary structure of proteins, depending on dose. WHC (1.88 ± 0.01%), OHC (1.76 ± 0.01%), and WSI (4.09 ± 0.02 g/g) increased at 10 kGy, compared with the control, verified the enhanced hydrolytic depolymerization of starch. Significant decrease in the viscosity parameters (peak, hold, final, and setback), G’ and G”, and significant increase in tan δ (1.37 × 10<sup>−1</sup>±0.02 to 2.43 × 10<sup>−1</sup>±0.05) was observed. The lowest gelatination temperatures (onset, peak, conclusion) and enthalpy change of gelatinization were observed in sample irradiated at 10 kGy, which was attributed to the highest damage in starch structure induced by gamma irradiation. A decrease in hardness with increasing doses of gamma irradiation indicated increased crystallization of amylopectin. The analysis of FTIR confirmed the effects of gamma irradiation on carbohydrate and water absorption capacity, showing a reduction in O–H stretching vibrations and increases in C–H stretching and C<img>O stretch, especially at 10 kGy. Scanning electron microscopy showed surface cracks and weakening of starch granules at 7.5 and 10 kGy. These results confirmed that higher doses affected technological properties and may be useful in food formulation.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"243 ","pages":"Article 113691"},"PeriodicalIF":2.8,"publicationDate":"2026-02-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146134651","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 : 2026-02-05DOI: 10.1016/j.radphyschem.2026.113660
A.V. Ponomarev, M.M. Belova
The influence of nitric acid and hydrocarbon diluent (from n-hexane to n-pentadecane; as well as isooctane) on the radiolytic formation of phosphorus-containing products in a 30 wt% solution of tri-n-butyl phosphate (TBP) was investigated. The efficient formation of nitro and hydroxy derivatives of TBP with a simultaneous decrease in the yield of alkyl phosphonates and alkyl phosphates is the main difference between the radiolysis of acidified and acid-free solutions. In general, the composition of radiolysis products depends on the diluent. At a dose of up to 30 kGy, the presence of nitric acid in the solution increases the yield of TBP degradation from an average of 74 to 90 nmol J−1, but this yield is practically independent of the number of C atoms in the diluent molecule.
{"title":"The combined effect of nitric acid and hydrocarbon diluent on the radiolytic transformations of tributyl phosphate","authors":"A.V. Ponomarev, M.M. Belova","doi":"10.1016/j.radphyschem.2026.113660","DOIUrl":"10.1016/j.radphyschem.2026.113660","url":null,"abstract":"<div><div>The influence of nitric acid and hydrocarbon diluent (from n-hexane to n-pentadecane; as well as isooctane) on the radiolytic formation of phosphorus-containing products in a 30 wt% solution of tri-<em>n</em>-butyl phosphate (TBP) was investigated. The efficient formation of nitro and hydroxy derivatives of TBP with a simultaneous decrease in the yield of alkyl phosphonates and alkyl phosphates is the main difference between the radiolysis of acidified and acid-free solutions. In general, the composition of radiolysis products depends on the diluent. At a dose of up to 30 kGy, the presence of nitric acid in the solution increases the yield of TBP degradation from an average of 74 to 90 nmol J<sup>−1</sup>, but this yield is practically independent of the number of C atoms in the diluent molecule.</div></div>","PeriodicalId":20861,"journal":{"name":"Radiation Physics and Chemistry","volume":"243 ","pages":"Article 113660"},"PeriodicalIF":2.8,"publicationDate":"2026-02-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146134655","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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