Applied Radiation and Isotopes最新文献

Evaluation of 18F-FDG absorbed dose ratios in percent in adult and pediatric reference phantoms using DoseCalcs Monte Carlo platform

IF 1.6 3区工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR

Applied Radiation and Isotopes

Pub Date : 2025-02-08 DOI: 10.1016/j.apradiso.2025.111705

Tarik El Ghalbzouri , Tarek El Bardouni , Jaafar El Bakkali , Hicham Satti , Abdelhamid Nouayti , Iman Berriban , Randa Yerrou , Assia Arectout , Maryam Hadouachi

This study investigates the field of radiation exposure in nuclear medicine, which might have implications for exposure to ionizing radiation in pediatric cases. To demonstrate the difference in radiosensitivity between younger patients and adults and to highlight the need for individualized radiation protection procedures when investigating medical imaging and therapy, this study examines the absorbed dose ratios in percent (ADR%) for ¹⁸F-FDG. This parameter is an important indicator, illustrating the percentage of radiation dose absorbed by specific organs/tissues concerning the emitted radiation from different body regions.

The methodology involves calculating ADR% in twelve voxel-based models for adults, children, and newborns, as referenced by International Commission on Radiological Protection (ICRP) Publications 110 and 143. The simulations used the ¹⁸F positron spectrum from ICRP Publication 107 and Livermore models. These simulations were performed using the DoseCalcs Monte Carlo platform.

We have calculated the S-values and ADR% using the DoseCalcs simulations of the ¹⁸F positrons and provided a comprehensive dataset of ADR% results. This dataset evaluates the impact of anatomical variation on absorbed dose in target regions. It consists of 141 target regions and 8 different source regions.

Significant differences in radiosensitivity were observed in ADR% values among various source–target combinations for each age and sex group. The self-irradiation ADR% reaches up to 95%, while the cross-irradiation ADR% varies, ranging approximately from 0.1% to 12%, depending on the mass of the target organ, the distance between it and the source organ, and the chemical composition of these organs. Also, the variations observed across different age and sex phantoms highlight the importance of personalized internal dosimetry, especially for pediatric cases with heightened radiosensitivity. Healthcare practitioners can use the dataset of ADR% values as the first stage to illustrate variability and optimize nuclear medicine imaging with ¹⁸F-FDG while reducing radiation risks.

{"title":"Evaluation of 18F-FDG absorbed dose ratios in percent in adult and pediatric reference phantoms using DoseCalcs Monte Carlo platform","authors":"Tarik El Ghalbzouri , Tarek El Bardouni , Jaafar El Bakkali , Hicham Satti , Abdelhamid Nouayti , Iman Berriban , Randa Yerrou , Assia Arectout , Maryam Hadouachi","doi":"10.1016/j.apradiso.2025.111705","DOIUrl":"10.1016/j.apradiso.2025.111705","url":null,"abstract":"<div><div>This study investigates the field of radiation exposure in nuclear medicine, which might have implications for exposure to ionizing radiation in pediatric cases. To demonstrate the difference in radiosensitivity between younger patients and adults and to highlight the need for individualized radiation protection procedures when investigating medical imaging and therapy, this study examines the absorbed dose ratios in percent (ADR%) for <sup>18</sup>F-FDG. This parameter is an important indicator, illustrating the percentage of radiation dose absorbed by specific organs/tissues concerning the emitted radiation from different body regions.</div><div>The methodology involves calculating ADR% in twelve voxel-based models for adults, children, and newborns, as referenced by International Commission on Radiological Protection (ICRP) Publications 110 and 143. The simulations used the <sup>18</sup>F positron spectrum from ICRP Publication 107 and Livermore models. These simulations were performed using the DoseCalcs Monte Carlo platform.</div><div>We have calculated the S-values and ADR% using the DoseCalcs simulations of the <sup>18</sup>F positrons and provided a comprehensive dataset of ADR% results. This dataset evaluates the impact of anatomical variation on absorbed dose in target regions. It consists of 141 target regions and 8 different source regions.</div><div>Significant differences in radiosensitivity were observed in ADR% values among various source–target combinations for each age and sex group. The self-irradiation ADR% reaches up to 95%, while the cross-irradiation ADR% varies, ranging approximately from 0.1% to 12%, depending on the mass of the target organ, the distance between it and the source organ, and the chemical composition of these organs. Also, the variations observed across different age and sex phantoms highlight the importance of personalized internal dosimetry, especially for pediatric cases with heightened radiosensitivity. Healthcare practitioners can use the dataset of ADR% values as the first stage to illustrate variability and optimize nuclear medicine imaging with <sup>18</sup>F-FDG while reducing radiation risks.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"218 ","pages":"Article 111705"},"PeriodicalIF":1.6,"publicationDate":"2025-02-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143369802","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

A methodology study for sodium quantification in bone and soft tissue based on in vivo neutron activation analysis using a two-compartment model

IF 1.6 3区工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR

Applied Radiation and Isotopes

Pub Date : 2025-02-07 DOI: 10.1016/j.apradiso.2025.111712

Song Yue , Mychaela Coyne , Connie M. Weaver , Cheryl AM. Anderson , Linda H. Nie

Sodium (Na) is an essential mineral for human health regulation and in excess has been associated with many diseases. Its storage has been found in rapidly (soft tissue) and slowly exchangeable pools (bone) in human body. However, Na concentration and metabolism information in human bone and soft tissue cannot be determined using conventional biological urine and blood samples. The aim of this study was to apply a transportable neutron generator based in vivo neutron activation analysis technique to separately quantify Na in bone and soft tissue. Two pigs were fed with low and high Na diet to investigate the effects of dietary Na intake on Na storage and metabolism. The emitted gamma rays from Na activated by thermal neutron capture reaction in pig leg were collected using a high purity germanium detector. A biokinetic model based on internal dosimetry theorem was developed to obtain the bone and soft tissue Na concentration, as well as half-life of Na retention in the two compartments. The results show that soft tissue Na concentration was significantly higher in the pig that received a high Na diet

(1057.08 \pm 43.62 p p m v s 704.46 \pm 45.60 p p m, p = 0.007)

. In contrast, the bone sodium concentration was not affected by dietary intervention

(856.45 \pm 78.48 p p m v s 803.30 \pm 48.98 p p m, p = 0.107)

. The developed methodology is capable of effectively measuring altered Na levels resulting from dietary Na consumption, with great potential in exploring the association between Na intake and health outcomes such as hypertension.

{"title":"A methodology study for sodium quantification in bone and soft tissue based on in vivo neutron activation analysis using a two-compartment model","authors":"Song Yue , Mychaela Coyne , Connie M. Weaver , Cheryl AM. Anderson , Linda H. Nie","doi":"10.1016/j.apradiso.2025.111712","DOIUrl":"10.1016/j.apradiso.2025.111712","url":null,"abstract":"<div><div>Sodium (Na) is an essential mineral for human health regulation and in excess has been associated with many diseases. Its storage has been found in rapidly (soft tissue) and slowly exchangeable pools (bone) in human body. However, Na concentration and metabolism information in human bone and soft tissue cannot be determined using conventional biological urine and blood samples. The aim of this study was to apply a transportable neutron generator based <em>in vivo</em> neutron activation analysis technique to separately quantify Na in bone and soft tissue. Two pigs were fed with low and high Na diet to investigate the effects of dietary Na intake on Na storage and metabolism. The emitted gamma rays from Na activated by thermal neutron capture reaction in pig leg were collected using a high purity germanium detector. A biokinetic model based on internal dosimetry theorem was developed to obtain the bone and soft tissue Na concentration, as well as half-life of Na retention in the two compartments. The results show that soft tissue Na concentration was significantly higher in the pig that received a high Na diet <span><math><mrow><mo>(</mo><mrow><mn>1057.08</mn><mspace></mspace><mo>±</mo><mn>43.62</mn><mspace></mspace><mi>p</mi><mi>p</mi><mi>m</mi><mspace></mspace><mi>v</mi><mi>s</mi><mspace></mspace><mn>704.46</mn><mspace></mspace><mo>±</mo><mn>45.60</mn><mspace></mspace><mi>p</mi><mi>p</mi><mi>m</mi><mo>,</mo><mi>p</mi><mo>=</mo><mn>0.007</mn></mrow><mo>)</mo></mrow></math></span>. In contrast, the bone sodium concentration was not affected by dietary intervention <span><math><mrow><mo>(</mo><mrow><mn>856.45</mn><mo>±</mo><mn>78.48</mn><mspace></mspace><mi>p</mi><mi>p</mi><mi>m</mi><mspace></mspace><mi>v</mi><mi>s</mi><mspace></mspace><mn>803.30</mn><mo>±</mo><mn>48.98</mn><mspace></mspace><mi>p</mi><mi>p</mi><mi>m</mi><mo>,</mo><mi>p</mi><mo>=</mo><mn>0.107</mn></mrow><mo>)</mo></mrow></math></span>. The developed methodology is capable of effectively measuring altered Na levels resulting from dietary Na consumption, with great potential in exploring the association between Na intake and health outcomes such as hypertension.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"218 ","pages":"Article 111712"},"PeriodicalIF":1.6,"publicationDate":"2025-02-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143369801","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Technetium-99m-labeled stealth liposomes: A new Strategy to Identify metastasis in tumour model

IF 1.6 3区工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR

Applied Radiation and Isotopes

Pub Date : 2025-02-06 DOI: 10.1016/j.apradiso.2025.111709

Swapna J. Nabar , Tanuja Shet , Basant Malpani , Puthusserickal Hassan , Sandip Basu

Objective

Stealth liposomes are useful carriers for delivering drugs to cancer sites. In this paper we describe the preparation and evaluation of ^99mTc labelled stealth liposomes (PEG-Liposomes) as potential radiopharmaceuticals for SPECT imaging of cancer. This study is first to describe targeted localisation of radiolabeled stealth liposomes in tumourous cells, sparing normal cells of various organs in metastatic L1210 mouse tumour model in BDF1 mice.

Methods

Glutathione encapsulated stealth liposomes were made using lipid film hydration technique followed by probe sonication. Liposomes were radiolabeled using a lipophilic technetium complex, ^99mTc-d,l-HMPAO. Labelled liposomes were purified by gel chromatography over sephadex G25 column. The tumour model was developed in immuno-competent BDF1 mice (F1DBA/2/C57-BL6 crosses) by injecting L1210 cells intraperitoneally. Biodistribution studies of the ^99mTc- stealth liposomes were done in both tumour induced and normal mice. Histopathologic studies were done by excising the organs and the radioactivity in various sections was detected by autoradiography.

Results

The stealth liposomes could be synthesized as per a reported procedure and it showed similar retention factor in thin layer chromatography. Liposomes could be radiolabelled by using ^99mTc-d,lHMPAO. Purification over sephadex G 25 column yielded radioachemical purity greater than 95%. Biodistribution studies and autoradiography studies showed significantly higher accumulation of ^99mTc labelled stealth liposomes in liver, pancreas and ascitic fluid of the tumour induced mice as compared to normal mice.

Conclusions

^99mTc labelled stealth liposomes having radiochemical purity greater than 95% could be prepared which showed higher uptake in tumour.

{"title":"Technetium-99m-labeled stealth liposomes: A new Strategy to Identify metastasis in tumour model","authors":"Swapna J. Nabar , Tanuja Shet , Basant Malpani , Puthusserickal Hassan , Sandip Basu","doi":"10.1016/j.apradiso.2025.111709","DOIUrl":"10.1016/j.apradiso.2025.111709","url":null,"abstract":"<div><h3>Objective</h3><div>Stealth liposomes are useful carriers for delivering drugs to cancer sites. In this paper we describe the preparation and evaluation of <sup>99m</sup>Tc labelled stealth liposomes (PEG-Liposomes) as potential radiopharmaceuticals for SPECT imaging of cancer. This study is first to describe targeted localisation of radiolabeled stealth liposomes in tumourous cells, sparing normal cells of various organs in metastatic L1210 mouse tumour model in BDF1 mice.</div></div><div><h3>Methods</h3><div>Glutathione encapsulated stealth liposomes were made using lipid film hydration technique followed by probe sonication. Liposomes were radiolabeled using a lipophilic technetium complex, <sup>99m</sup>Tc-d,l-HMPAO. Labelled liposomes were purified by gel chromatography over sephadex G25 column. The tumour model was developed in immuno-competent BDF1 mice (F1DBA/2/C57-BL6 crosses) by injecting L1210 cells intraperitoneally. Biodistribution studies of the <sup>99m</sup>Tc- stealth liposomes were done in both tumour induced and normal mice. Histopathologic studies were done by excising the organs and the radioactivity in various sections was detected by autoradiography.</div></div><div><h3>Results</h3><div>The stealth liposomes could be synthesized as per a reported procedure and it showed similar retention factor in thin layer chromatography. Liposomes could be radiolabelled by using <sup>99m</sup>Tc-d,lHMPAO. Purification over sephadex G 25 column yielded radioachemical purity greater than 95%. Biodistribution studies and autoradiography studies showed significantly higher accumulation of <sup>99m</sup>Tc labelled stealth liposomes in liver, pancreas and ascitic fluid of the tumour induced mice as compared to normal mice.</div></div><div><h3>Conclusions</h3><div><sup>99m</sup>Tc labelled stealth liposomes having radiochemical purity greater than 95% could be prepared which showed higher uptake in tumour.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"218 ","pages":"Article 111709"},"PeriodicalIF":1.6,"publicationDate":"2025-02-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143369798","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Production, radiochemical separation and electrochemical concentration of No-carrier-added 52Mn: An emerging PET radiometal

IF 1.6 3区工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR

Applied Radiation and Isotopes

Pub Date : 2025-02-05 DOI: 10.1016/j.apradiso.2025.111707

Sourav Patra , Sanchita Ghosh , Khajan Singh , Suresh Chand Sharma , Sanjay Vishwanath Thakare , Rubel Chakravarty

Recently, there has been significant interest in ⁵²Mn (T_½ = 5.6 d) as a relatively long lived radiometal for PET imaging of cancer. In this study, we have produced ⁵²Mn from natural Cr metallic powder target via ⁵²Cr (p, n) ⁵²Mn reaction in a particle accelerator. An efficient radiochemical separation method based on selective precipitation of Cr as Cr(OH)₃ followed by electrochemical purification and concentration of ⁵²Mn was developed for isolation of no-carrier-added (nca) ⁵²Mn from the irradiated target. The overall radiochemical separation yield of the process was >75 %. After separation, ⁵²Mn was obtained with >99.5 % radionuclidic purity and >97 % radiochemical purity. The apparent molar activity of ⁵²Mn was determined to be 2.2 ± 0.1 MBq/nmol and it was found suitable for preparation of radiopharmaceuticals. As a proof of concept, [⁵²Mn]Mn-DOTA-E[c(RGDfK)]₂ was prepared with 98.8 ± 0.4 % radiolabeling yield and the radiochemical stability of the formulation was maintained over a period of 7 days under physiological conditions. Overall, this strategy is viable for obtaining nca ⁵²Mn in a suitable form for radiopharmaceutical preparation and would potentially increase the availability of this radiometal for clinical PET imaging in foreseeable future.

{"title":"Production, radiochemical separation and electrochemical concentration of No-carrier-added 52Mn: An emerging PET radiometal","authors":"Sourav Patra , Sanchita Ghosh , Khajan Singh , Suresh Chand Sharma , Sanjay Vishwanath Thakare , Rubel Chakravarty","doi":"10.1016/j.apradiso.2025.111707","DOIUrl":"10.1016/j.apradiso.2025.111707","url":null,"abstract":"<div><div>Recently, there has been significant interest in <sup>52</sup>Mn (T<sub>½</sub> = 5.6 d) as a relatively long lived radiometal for PET imaging of cancer. In this study, we have produced <sup>52</sup>Mn from natural Cr metallic powder target via <sup>52</sup>Cr (p, n) <sup>52</sup>Mn reaction in a particle accelerator. An efficient radiochemical separation method based on selective precipitation of Cr as Cr(OH)<sub>3</sub> followed by electrochemical purification and concentration of <sup>52</sup>Mn was developed for isolation of no-carrier-added (nca) <sup>52</sup>Mn from the irradiated target. The overall radiochemical separation yield of the process was >75 %. After separation, <sup>52</sup>Mn was obtained with >99.5 % radionuclidic purity and >97 % radiochemical purity. The apparent molar activity of <sup>52</sup>Mn was determined to be 2.2 ± 0.1 MBq/nmol and it was found suitable for preparation of radiopharmaceuticals. As a proof of concept, [<sup>52</sup>Mn]Mn-DOTA-E[c(RGDfK)]<sub>2</sub> was prepared with 98.8 ± 0.4 % radiolabeling yield and the radiochemical stability of the formulation was maintained over a period of 7 days under physiological conditions. Overall, this strategy is viable for obtaining nca <sup>52</sup>Mn in a suitable form for radiopharmaceutical preparation and would potentially increase the availability of this radiometal for clinical PET imaging in foreseeable future.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"218 ","pages":"Article 111707"},"PeriodicalIF":1.6,"publicationDate":"2025-02-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143369799","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Preliminary experiments to produce lutetium-177 in the TRR-1/M1 Thai research reactor

IF 1.6 3区工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR

Applied Radiation and Isotopes

Pub Date : 2025-02-05 DOI: 10.1016/j.apradiso.2025.111708

Pitima Ragchana , Phannee Saengkaew , Saensuk Wetchagarun , Kanokrat Tiyapun , Moleephan Dangprasert , Kitiwat Khamwan

Lutetium-177 has emerged as a highly efficient radionuclide for medical applications, particularly in the field of targeted radionuclide therapy. Its production has been increasingly optimized through neutron activation techniques, which offer distinct advantages over alternative methods. Utilizing the TRR-1/M1 research reactor, which has been in operation for nearly six decades, provides a strategic opportunity for advancing domestic radioisotope production, thereby supporting the medical sector in Thailand. The TRR-1/M1 reactor, despite its operational age, continues to exhibit considerable potential for contributing to medical research and radioisotope development in Thailand. Preliminary experimental results, conducted at a flux of 1.42 × 10¹² n/cm²/s demonstrated promising outcomes, even under operational constraints such as fuel management limitations. Notably, the direct neutron activation of natural lutetium oxide notably yielded a specific activity of ¹⁷⁷Lu at 10.92 GBq/g (295.06 mCi/g) with a production yield of 44.8%, with projections reaching 222 GBq/g (6 Ci/g) after 40 days of neutron irradiation. In comparison, the indirect method, using natural ytterbium oxide as a precursor, achieved a maximum specific activity of ¹⁷⁷Lu at 6.6 MBq/g (180.3 μCi/g) with a yield of 37.8% of a theoretical maximum of 17.6 MBq/g (476 μCi/g) after only 10 h of neutron activation. These results highlight the feasibility and promise of ¹⁷⁷Lu radioisotope production in Thailand.

{"title":"Preliminary experiments to produce lutetium-177 in the TRR-1/M1 Thai research reactor","authors":"Pitima Ragchana , Phannee Saengkaew , Saensuk Wetchagarun , Kanokrat Tiyapun , Moleephan Dangprasert , Kitiwat Khamwan","doi":"10.1016/j.apradiso.2025.111708","DOIUrl":"10.1016/j.apradiso.2025.111708","url":null,"abstract":"<div><div>Lutetium-177 has emerged as a highly efficient radionuclide for medical applications, particularly in the field of targeted radionuclide therapy. Its production has been increasingly optimized through neutron activation techniques, which offer distinct advantages over alternative methods. Utilizing the TRR-1/M1 research reactor, which has been in operation for nearly six decades, provides a strategic opportunity for advancing domestic radioisotope production, thereby supporting the medical sector in Thailand. The TRR-1/M1 reactor, despite its operational age, continues to exhibit considerable potential for contributing to medical research and radioisotope development in Thailand. Preliminary experimental results, conducted at a flux of 1.42 × 10<sup>12</sup> n/cm<sup>2</sup>/s demonstrated promising outcomes, even under operational constraints such as fuel management limitations. Notably, the direct neutron activation of natural lutetium oxide notably yielded a specific activity of <sup>177</sup>Lu at 10.92 GBq/g (295.06 mCi/g) with a production yield of 44.8%, with projections reaching 222 GBq/g (6 Ci/g) after 40 days of neutron irradiation. In comparison, the indirect method, using natural ytterbium oxide as a precursor, achieved a maximum specific activity of <sup>177</sup>Lu at 6.6 MBq/g (180.3 μCi/g) with a yield of 37.8% of a theoretical maximum of 17.6 MBq/g (476 μCi/g) after only 10 h of neutron activation. These results highlight the feasibility and promise of <sup>177</sup>Lu radioisotope production in Thailand.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"218 ","pages":"Article 111708"},"PeriodicalIF":1.6,"publicationDate":"2025-02-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143349438","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Structural and thermal insights into the luminescent behavior of Dy³⁺-Doped BaZrO₃ with alkali metal codopants under UV radiation

IF 1.6 3区工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR

Applied Radiation and Isotopes

Pub Date : 2025-02-03 DOI: 10.1016/j.apradiso.2025.111698

Y. Tuncer Arslanlar , Y. Alajlani , M.B. Coban , U.H. Kaynar , H. Aydin , H. Örücü , J. Garcia Guinea , N. Can

This study investigates the structural, thermal, and photoluminescent properties of Dy³⁺-doped BaZrO₃ (BZO) perovskites, synthesized via a co-precipitation method, incorporating alkali metal codopants (Li⁺, Na⁺, and K⁺). X-ray diffraction (XRD) analysis confirmed the retention of the cubic perovskite phase following doping, with Rietveld refinement further revealing minor lattice distortions due to Dy³⁺ incorporation. The Williamson-Hall (W–H) analysis revealed average crystallite sizes of 53 nm and 66 nm for undoped and 0.01 Dy³⁺-doped BaZrO₃, respectively, with corresponding micro-strain values of 1.79 × 10⁻³ and 1.81 × 10⁻³, suggesting lattice distortions due to incorporation of Dy³⁺. Fourier transform infrared (FTIR) spectroscopy confirmed the cubic perovskite structure and subtle structural modifications upon doping. Notably, the absence of moisture-related peaks highlights the effectiveness of the synthesis process, including rigorous drying and calcination steps that prevented hydrous species. Photoluminescence (PL) analysis of Dy³⁺-doped BaZrO₃ exhibited three prominent emission peaks at 452 nm, 573 nm, and 656 nm under 368 nm excitation. These peaks correspond to the characteristic intra-4f electronic transitions of Dy³⁺ ions, specifically, ⁴I_13/2 to ⁶H_15/2, ⁴F_9/2 to ⁶H_13/2, and ⁴F_9/2 to ⁶H_11/2, representing blue, yellow, and red emissions, respectively. Photoluminescence decay studies showed multi-exponential behavior, with the average lifetime decreasing from 641 μs in undoped BZO to 492 μs in Dy³⁺-doped samples attributed to enhanced non-radiative recombination pathways. Among the codopants, Li⁺ demonstrated the most significant improvement in luminescence intensity and thermal stability by mitigating defects and optimizing charge compensation.

{"title":"Structural and thermal insights into the luminescent behavior of Dy³⁺-Doped BaZrO₃ with alkali metal codopants under UV radiation","authors":"Y. Tuncer Arslanlar , Y. Alajlani , M.B. Coban , U.H. Kaynar , H. Aydin , H. Örücü , J. Garcia Guinea , N. Can","doi":"10.1016/j.apradiso.2025.111698","DOIUrl":"10.1016/j.apradiso.2025.111698","url":null,"abstract":"<div><div>This study investigates the structural, thermal, and photoluminescent properties of Dy³⁺-doped BaZrO₃ (BZO) perovskites, synthesized via a co-precipitation method, incorporating alkali metal codopants (Li⁺, Na⁺, and K⁺). X-ray diffraction (XRD) analysis confirmed the retention of the cubic perovskite phase following doping, with Rietveld refinement further revealing minor lattice distortions due to Dy³⁺ incorporation. The Williamson-Hall (W–H) analysis revealed average crystallite sizes of 53 nm and 66 nm for undoped and 0.01 Dy³⁺-doped BaZrO₃, respectively, with corresponding micro-strain values of 1.79 × 10⁻³ and 1.81 × 10⁻³, suggesting lattice distortions due to incorporation of Dy³⁺. Fourier transform infrared (FTIR) spectroscopy confirmed the cubic perovskite structure and subtle structural modifications upon doping. Notably, the absence of moisture-related peaks highlights the effectiveness of the synthesis process, including rigorous drying and calcination steps that prevented hydrous species. Photoluminescence (PL) analysis of Dy³⁺-doped BaZrO₃ exhibited three prominent emission peaks at 452 nm, 573 nm, and 656 nm under 368 nm excitation. These peaks correspond to the characteristic intra-4f electronic transitions of Dy³⁺ ions, specifically, <sup>4</sup>I<sub>13/2</sub> to <sup>6</sup>H<sub>15/2</sub>, <sup>4</sup>F<sub>9/2</sub> to <sup>6</sup>H<sub>13/2</sub>, and <sup>4</sup>F<sub>9/2</sub> to <sup>6</sup>H<sub>11/2</sub>, representing blue, yellow, and red emissions, respectively. Photoluminescence decay studies showed multi-exponential behavior, with the average lifetime decreasing from 641 μs in undoped BZO to 492 μs in Dy³⁺-doped samples attributed to enhanced non-radiative recombination pathways. Among the codopants, Li⁺ demonstrated the most significant improvement in luminescence intensity and thermal stability by mitigating defects and optimizing charge compensation.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"218 ","pages":"Article 111698"},"PeriodicalIF":1.6,"publicationDate":"2025-02-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143284278","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Evaluating cosmic-ray backgrounds in HPGe gamma spectrometry: Experimental observations and GEANT4 simulations

IF 1.6 3区工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR

Applied Radiation and Isotopes

Pub Date : 2025-01-31 DOI: 10.1016/j.apradiso.2025.111703

Zaijing Sun , Krishnakumar Divakar Nangeelil , Sungmin Pak

This study demonstrates the efficacy of employing the GEANT4 simulation toolkit for investigating the background spectra of High Purity Germanium (HPGe) detector induced by atmospheric cosmic rays. GEANT4 is utilized to accurately replicate the experimental setup, detector geometry, and the gamma background spectrum for the HPGe detector. The EXPAC model is used to generate above-ground-level cosmic-ray particles for the terrain. Various techniques, such as the use of low-activity lead and oxygen-free copper as shielding materials, along with an external plastic scintillator to veto cosmic rays from the atmosphere, are employed to improve the signal-to-background ratio of HPGe detector systems. Photopeaks associated with ⁴⁰K, ⁶⁰Co, ²³²Th and ²³⁸U decay chain were observed in the measured background gamma spectrum. The integral count rates of the experimental and simulated background spectrum in the 20–1750 keV energy range were 1.92 ± 0.06 s⁻¹ and 1.84 ± 0.14 s⁻¹, respectively. The experimental and simulated background spectra match well, both qualitatively and quantitatively, indicating that GEANT4 is an effective simulation tool for predicting gamma spectra of HPGe detectors accurately.

{"title":"Evaluating cosmic-ray backgrounds in HPGe gamma spectrometry: Experimental observations and GEANT4 simulations","authors":"Zaijing Sun , Krishnakumar Divakar Nangeelil , Sungmin Pak","doi":"10.1016/j.apradiso.2025.111703","DOIUrl":"10.1016/j.apradiso.2025.111703","url":null,"abstract":"<div><div>This study demonstrates the efficacy of employing the GEANT4 simulation toolkit for investigating the background spectra of High Purity Germanium (HPGe) detector induced by atmospheric cosmic rays. GEANT4 is utilized to accurately replicate the experimental setup, detector geometry, and the gamma background spectrum for the HPGe detector. The EXPAC model is used to generate above-ground-level cosmic-ray particles for the terrain. Various techniques, such as the use of low-activity lead and oxygen-free copper as shielding materials, along with an external plastic scintillator to veto cosmic rays from the atmosphere, are employed to improve the signal-to-background ratio of HPGe detector systems. Photopeaks associated with <sup>40</sup>K, <sup>60</sup>Co, <sup>232</sup>Th and <sup>238</sup>U decay chain were observed in the measured background gamma spectrum. The integral count rates of the experimental and simulated background spectrum in the 20–1750 keV energy range were 1.92 ± 0.06 s<sup>−1</sup> and 1.84 ± 0.14 s<sup>−1</sup>, respectively. The experimental and simulated background spectra match well, both qualitatively and quantitatively, indicating that GEANT4 is an effective simulation tool for predicting gamma spectra of HPGe detectors accurately.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"218 ","pages":"Article 111703"},"PeriodicalIF":1.6,"publicationDate":"2025-01-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143103010","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Corrigendum to "Development of a CLYC-based wide dose rate range portable neutron-gamma detector" [Appl. Radiat. Isotop. 217 111629].

IF 1.6 3区工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR

Applied Radiation and Isotopes

Pub Date : 2025-01-31 DOI: 10.1016/j.apradiso.2025.111694

Yuliang Huang

引用次数: 0

Characterization of material using dual-energy gamma-ray tomography: Determination of atomic number and density

IF 1.6 3区工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR

Applied Radiation and Isotopes

Pub Date : 2025-01-29 DOI: 10.1016/j.apradiso.2025.111702

Patrício Luiz de Andrade , Enivaldo Santos Barbosa, Daniel Milian Pérez, Abel Gámez Rodríguez, Marcio Fernando Paixão de Brito, Carlos Costa Dantas, Antonio Celso Dantas Antonino

This study presents a new mathematical model for determining the atomic number and density of materials using dual-energy gamma-ray transmission tomography. The proposed method is based on an algebraic function that relates the atomic number to the attenuation ratio, offering an innovative approach for the precise characterization of materials. The methodology employed involved the theoretical development of the model, followed by tests using data from NIST XCOM and practical experiments with a gamma-ray transmission tomograph using americium-241 (59.5 keV) and cesium-137 (662 keV) sources. Two sets of materials were used: one group of 10 elements for determining the calibration curves and another with 4 elements (graphite, magnesium, aluminum, and iron) for validating the theoretical and experimental calibration curves. Unlike existing methods, which predominantly utilize polynomial or exponential relationships, the proposed model introduces a novel algebraic approach to enhance accuracy and computational efficiency. The performance of the new model was compared with approaches used by other authors. The analyses were conducted for elements with atomic numbers between 6 and 30, covering a significant range of materials of practical and scientific interest. The results demonstrated that the proposed model presented discrepancies of less than 3.5% for the atomic number and a maximum error of 10.04% for the density, with a trend of decreasing errors as the atomic number increased.

{"title":"Characterization of material using dual-energy gamma-ray tomography: Determination of atomic number and density","authors":"Patrício Luiz de Andrade , Enivaldo Santos Barbosa, Daniel Milian Pérez, Abel Gámez Rodríguez, Marcio Fernando Paixão de Brito, Carlos Costa Dantas, Antonio Celso Dantas Antonino","doi":"10.1016/j.apradiso.2025.111702","DOIUrl":"10.1016/j.apradiso.2025.111702","url":null,"abstract":"<div><div>This study presents a new mathematical model for determining the atomic number and density of materials using dual-energy gamma-ray transmission tomography. The proposed method is based on an algebraic function that relates the atomic number to the attenuation ratio, offering an innovative approach for the precise characterization of materials. The methodology employed involved the theoretical development of the model, followed by tests using data from NIST XCOM and practical experiments with a gamma-ray transmission tomograph using americium-241 (59.5 keV) and cesium-137 (662 keV) sources. Two sets of materials were used: one group of 10 elements for determining the calibration curves and another with 4 elements (graphite, magnesium, aluminum, and iron) for validating the theoretical and experimental calibration curves. Unlike existing methods, which predominantly utilize polynomial or exponential relationships, the proposed model introduces a novel algebraic approach to enhance accuracy and computational efficiency. The performance of the new model was compared with approaches used by other authors. The analyses were conducted for elements with atomic numbers between 6 and 30, covering a significant range of materials of practical and scientific interest. The results demonstrated that the proposed model presented discrepancies of less than 3.5% for the atomic number and a maximum error of 10.04% for the density, with a trend of decreasing errors as the atomic number increased.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"218 ","pages":"Article 111702"},"PeriodicalIF":1.6,"publicationDate":"2025-01-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143078507","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Investigation on radiation interactions with some quenched alloys used in nuclear reactors

IF 1.6 3区工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR

Applied Radiation and Isotopes

Pub Date : 2025-01-28 DOI: 10.1016/j.apradiso.2025.111701

Hasan Oğul , Abuzer Yaz , Hakan Us , Fatih Bulut

This study presents the investigation of the radiation interaction properties for SS304 and Incoloy 800H alloys, which are widely used in PWRs and HTGRs. First of all, theoretical and MC simulation evaluations are performed, then experiments are conducted for further analysis. The findings indicate no significant difference in mass attenuation coefficients (MAC) and gamma-ray radiation protection efficiencies (RPE) between the two alloys. Additionally, both SS304 and Incoloy 800H exhibit similar neutron shielding capabilities, with comparable effective removal cross-sections and numbers of transmitted neutrons at different neutron energies (0.025 eV, 100 eV and 4.5 MeV). The study also examines secondary radiation generated by neutron interactions. The impact of thermal treatment (300 °C, 500 °C, 700 °C and 1000 °C) and cooling approaches (quenching and self-cooling) on these alloys were further experimentally examined. Notably, thermal treatment changes the MAC values, particularly at 1000 °C, with SS304 showing a more distinct change than Incoloy 800H. Besides, quenched samples have higher MAC values compared to self-cooled samples, especially at 1000 °C. However, the microhardness values remained largely unaffected by heat treatment, except at 1000 °C, where both alloys exhibited reduced microhardness. The study underscores that there is no significant difference in microhardness between quenching and self-cooling techniques. These results provide valuable insights for enhancing the safety and efficiency of radiation shielding materials in nuclear reactors.

{"title":"Investigation on radiation interactions with some quenched alloys used in nuclear reactors","authors":"Hasan Oğul , Abuzer Yaz , Hakan Us , Fatih Bulut","doi":"10.1016/j.apradiso.2025.111701","DOIUrl":"10.1016/j.apradiso.2025.111701","url":null,"abstract":"<div><div>This study presents the investigation of the radiation interaction properties for SS304 and Incoloy 800H alloys, which are widely used in PWRs and HTGRs. First of all, theoretical and MC simulation evaluations are performed, then experiments are conducted for further analysis. The findings indicate no significant difference in mass attenuation coefficients (MAC) and gamma-ray radiation protection efficiencies (RPE) between the two alloys. Additionally, both SS304 and Incoloy 800H exhibit similar neutron shielding capabilities, with comparable effective removal cross-sections and numbers of transmitted neutrons at different neutron energies (0.025 eV, 100 eV and 4.5 MeV). The study also examines secondary radiation generated by neutron interactions. The impact of thermal treatment (300 °C, 500 °C, 700 °C and 1000 °C) and cooling approaches (quenching and self-cooling) on these alloys were further experimentally examined. Notably, thermal treatment changes the MAC values, particularly at 1000 °C, with SS304 showing a more distinct change than Incoloy 800H. Besides, quenched samples have higher MAC values compared to self-cooled samples, especially at 1000 °C. However, the microhardness values remained largely unaffected by heat treatment, except at 1000 °C, where both alloys exhibited reduced microhardness. The study underscores that there is no significant difference in microhardness between quenching and self-cooling techniques. These results provide valuable insights for enhancing the safety and efficiency of radiation shielding materials in nuclear reactors.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"218 ","pages":"Article 111701"},"PeriodicalIF":1.6,"publicationDate":"2025-01-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143073593","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0