Durgaprasad Dakinedi, S. Adhya, S. Pal, K. Venkataramana
The pressurized heavy-water reactors (PHWR) consist of a low-pressure horizontal reactor vessel, calandria, containing heavy water as moderator. The calandria is pierced by a large number of coolant tubes (also called pressure tubes [PTs], 392 in 540 MWe PHWR), which contains fuel bundles, and through which pressurized heavy-water coolant circulates. During biennial shut down in 2017, in-service inspection of coolant channels in Tarapur atomic power station-4 (TAPS-4) had been carried out and after the review of results of inspection, it was recommended by various groups of experts that channel L-08 should be removed for postirradiation examination at Bhabha Atomic Research Center (BARC). Before the channel removal job, one special shielding flask was designed to shift the removed channel to BARC. The integrity test of special shielding flask was carried out by safely placing cobalt-60 (source strength 851000 MBq) capsule source inside the shielding flask with the help of cranking unit mechanism followed by dose rate mapping on the outer surface of the flask. To establish the hydrogen pickup rates in L-08 PT, sliver samples were collected and separately sent to BARC. Four metallic sliver samples were obtained at four different distances from north E-face. The activity content present in each sliver sample was also estimated. The maximum activity estimated was 2313.24 MBq. Subsequently, L-08 coolant channel was cut from both sides using a chipless tool. Jobs involving heavy water (D2O) collection work were carried out with a ventilated plastic suit. Derived air concentration (DAC) of tritium at the work location was maintained below 1DAC during the entire activity. Particulate DAC was found below the detectable limit. Floor contamination checks and floor decontamination were conducted at regular intervals to avoid buildup of contamination. As a result of such high-quality radiological safety measures, only 25 workers, out of 270 radiation workers, have received a cumulative dose of more than 3 mSv in direct reading dosimeter with a maximum individual dose of 8.45 mSv and maximum individual uptake of 0.39 GBq/m3. Job was completed with a total collective dose of 324.35P-mSv which is 14.5% lower than estimated. This article highlights some of the critical tasks involved in the cutting and the removal of irradiated coolant channel from the core of 540 Mwe TAPS-4 reactor which is a first of kind activity in nature.
{"title":"Radiological aspects during cutting and removal of L-08 coolant channel from the core of 540 MWe TAPS-4 nuclear reactor","authors":"Durgaprasad Dakinedi, S. Adhya, S. Pal, K. Venkataramana","doi":"10.4103/rpe.rpe_24_21","DOIUrl":"https://doi.org/10.4103/rpe.rpe_24_21","url":null,"abstract":"The pressurized heavy-water reactors (PHWR) consist of a low-pressure horizontal reactor vessel, calandria, containing heavy water as moderator. The calandria is pierced by a large number of coolant tubes (also called pressure tubes [PTs], 392 in 540 MWe PHWR), which contains fuel bundles, and through which pressurized heavy-water coolant circulates. During biennial shut down in 2017, in-service inspection of coolant channels in Tarapur atomic power station-4 (TAPS-4) had been carried out and after the review of results of inspection, it was recommended by various groups of experts that channel L-08 should be removed for postirradiation examination at Bhabha Atomic Research Center (BARC). Before the channel removal job, one special shielding flask was designed to shift the removed channel to BARC. The integrity test of special shielding flask was carried out by safely placing cobalt-60 (source strength 851000 MBq) capsule source inside the shielding flask with the help of cranking unit mechanism followed by dose rate mapping on the outer surface of the flask. To establish the hydrogen pickup rates in L-08 PT, sliver samples were collected and separately sent to BARC. Four metallic sliver samples were obtained at four different distances from north E-face. The activity content present in each sliver sample was also estimated. The maximum activity estimated was 2313.24 MBq. Subsequently, L-08 coolant channel was cut from both sides using a chipless tool. Jobs involving heavy water (D2O) collection work were carried out with a ventilated plastic suit. Derived air concentration (DAC) of tritium at the work location was maintained below 1DAC during the entire activity. Particulate DAC was found below the detectable limit. Floor contamination checks and floor decontamination were conducted at regular intervals to avoid buildup of contamination. As a result of such high-quality radiological safety measures, only 25 workers, out of 270 radiation workers, have received a cumulative dose of more than 3 mSv in direct reading dosimeter with a maximum individual dose of 8.45 mSv and maximum individual uptake of 0.39 GBq/m3. Job was completed with a total collective dose of 324.35P-mSv which is 14.5% lower than estimated. This article highlights some of the critical tasks involved in the cutting and the removal of irradiated coolant channel from the core of 540 Mwe TAPS-4 reactor which is a first of kind activity in nature.","PeriodicalId":32488,"journal":{"name":"Radiation Protection and Environment","volume":"44 1","pages":"61 - 66"},"PeriodicalIF":0.0,"publicationDate":"2021-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"46903049","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"ICRP Recommendations: Fit for purpose","authors":"D. Rao","doi":"10.4103/rpe.rpe_37_21","DOIUrl":"https://doi.org/10.4103/rpe.rpe_37_21","url":null,"abstract":"","PeriodicalId":32488,"journal":{"name":"Radiation Protection and Environment","volume":"44 1","pages":"59 - 60"},"PeriodicalIF":0.0,"publicationDate":"2021-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"42367566","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
The simultaneous measurements of atmospheric radon, ambient gamma radiations dose, and relevant meteorological parameters were carried out at the National Atmospheric Research Laboratory (NARL), Gadanki, India (13.459° N, 79.175° E) during June 2013–May 2014 are analyzed and presented. The results show that radon strongly correlates with temperature, relative humidity, and a weak correlation with air pressure, ambient gamma dose during fair weather days. Radon's well-defined monthly variability is observed, with the highest during winter and lowest during monsoon season. The fast Fourier transform analysis revealed a hidden memory in variations in radon activity with prominent peaks at 24 h and 12 h, indicating the influence of atmospheric stability on the abundance of radon in air. About 99% of radon activity lies below 70 Bq/m3 with a mean value of 11.81 ± 4.83 Bq/m3, and about 99% ambient gamma dose levels range from 140 to 240 nSv/h at NARL with a mean value of 192.17 ± 17.43 nSv/h. The ambient gamma dose levels are well within limits prescribed by the UNSCEAR.
{"title":"One year of 222Rn concentration at a typical rural site in South India","authors":"K. Kumar, Nagaraja Kamsali","doi":"10.4103/rpe.rpe_21_21","DOIUrl":"https://doi.org/10.4103/rpe.rpe_21_21","url":null,"abstract":"The simultaneous measurements of atmospheric radon, ambient gamma radiations dose, and relevant meteorological parameters were carried out at the National Atmospheric Research Laboratory (NARL), Gadanki, India (13.459° N, 79.175° E) during June 2013–May 2014 are analyzed and presented. The results show that radon strongly correlates with temperature, relative humidity, and a weak correlation with air pressure, ambient gamma dose during fair weather days. Radon's well-defined monthly variability is observed, with the highest during winter and lowest during monsoon season. The fast Fourier transform analysis revealed a hidden memory in variations in radon activity with prominent peaks at 24 h and 12 h, indicating the influence of atmospheric stability on the abundance of radon in air. About 99% of radon activity lies below 70 Bq/m3 with a mean value of 11.81 ± 4.83 Bq/m3, and about 99% ambient gamma dose levels range from 140 to 240 nSv/h at NARL with a mean value of 192.17 ± 17.43 nSv/h. The ambient gamma dose levels are well within limits prescribed by the UNSCEAR.","PeriodicalId":32488,"journal":{"name":"Radiation Protection and Environment","volume":"44 1","pages":"73 - 78"},"PeriodicalIF":0.0,"publicationDate":"2021-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"47179723","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Deepak Kumar, Y. Gautam, A. Sharma, Vineet Kumar, A. Tripathi, S. Kumar, J. Kumar, I. Saradhi, A. Kumar
This paper presents the activity concentrations of naturally occurring radionuclide 226Ra, 232Th, and 40K and the anthropogenic radionuclide, 137Cs in soil samples collected from Ballia and Deoria district of Uttar Pradesh, India. The mean activity concentrations of radionuclides in 43 soil samples from the two districts were measured using HPGe gamma spectrometry system. The activity level in soil samples varied from 23 to 50 Bq/kg with a mean of 30 Bq/kg for 226Ra, 30–74 Bq/kg with a mean of 47 Bq/kg for 232Th, 287–728 Bq/kg with a mean of 466 Bq/kg for 40K, and ≤0.1–1.4 Bq/kg with a mean of 0.4 Bq/kg for137Cs. The mean activity of naturally occurring 226Ra and 232Th is comparable with the international values reported by UNSCEAR while concentration of 40K is slightly higher. 137Cs activity is found to be comparable with the activities reported at other parts of India. Correlation of 226Ra and 40K activity with 232Th activity was observed as 0.85 and 0.75, respectively. A positive correlation (0.71) between 40K and 137Cs was found in the present study. The absorbed gamma dose rates in air were in the range of 44.6–98.3 nGy/h with a mean of 63.4 nGy/h, while the annual effective dose rates were observed in the range of 54.7–120.6 μSv/y with a mean of 77.8 μSv/y. The average value of radium equivalent activity in soil was 136.9 Bq/kg. This study provides a baseline data of natural radioactivity and 137Cs activity in soils of these two districts.
{"title":"Distribution of natural and artificial radioactivity concentration in soils of two districts (Ballia and Deoria) of Uttar Pradesh, India","authors":"Deepak Kumar, Y. Gautam, A. Sharma, Vineet Kumar, A. Tripathi, S. Kumar, J. Kumar, I. Saradhi, A. Kumar","doi":"10.4103/rpe.rpe_23_21","DOIUrl":"https://doi.org/10.4103/rpe.rpe_23_21","url":null,"abstract":"This paper presents the activity concentrations of naturally occurring radionuclide 226Ra, 232Th, and 40K and the anthropogenic radionuclide, 137Cs in soil samples collected from Ballia and Deoria district of Uttar Pradesh, India. The mean activity concentrations of radionuclides in 43 soil samples from the two districts were measured using HPGe gamma spectrometry system. The activity level in soil samples varied from 23 to 50 Bq/kg with a mean of 30 Bq/kg for 226Ra, 30–74 Bq/kg with a mean of 47 Bq/kg for 232Th, 287–728 Bq/kg with a mean of 466 Bq/kg for 40K, and ≤0.1–1.4 Bq/kg with a mean of 0.4 Bq/kg for137Cs. The mean activity of naturally occurring 226Ra and 232Th is comparable with the international values reported by UNSCEAR while concentration of 40K is slightly higher. 137Cs activity is found to be comparable with the activities reported at other parts of India. Correlation of 226Ra and 40K activity with 232Th activity was observed as 0.85 and 0.75, respectively. A positive correlation (0.71) between 40K and 137Cs was found in the present study. The absorbed gamma dose rates in air were in the range of 44.6–98.3 nGy/h with a mean of 63.4 nGy/h, while the annual effective dose rates were observed in the range of 54.7–120.6 μSv/y with a mean of 77.8 μSv/y. The average value of radium equivalent activity in soil was 136.9 Bq/kg. This study provides a baseline data of natural radioactivity and 137Cs activity in soils of these two districts.","PeriodicalId":32488,"journal":{"name":"Radiation Protection and Environment","volume":"44 1","pages":"67 - 72"},"PeriodicalIF":0.0,"publicationDate":"2021-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"44684445","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
V. Thakur, A. Jain, P. Sawant, P. Ashokkumar, L. Chaudhari, Probal Chaudhury
This article presents the design and development of a digital desktop gamma radiation monitoring system using Geiger–Muller tube detector and microcontroller. The radiation detector, battery, signal processing circuits, and the microcontroller board are housed inside a tabletop wooden model with an analog watch and a digital display of radiation dose rate. The alarm level has been set at 1 μSv/h and indicated through buzzer and LED. The system has been calibrated using 137Cs standard source and has a sensitivity of 0.7364 cps/μSv/h. This model can be displayed on any table/desk or kept near a doorway to continuously monitor background radiation level, without drawing public attention, to detect any movement or presence of radiation source.
{"title":"Development of a desktop radiation monitoring system","authors":"V. Thakur, A. Jain, P. Sawant, P. Ashokkumar, L. Chaudhari, Probal Chaudhury","doi":"10.4103/rpe.rpe_6_21","DOIUrl":"https://doi.org/10.4103/rpe.rpe_6_21","url":null,"abstract":"This article presents the design and development of a digital desktop gamma radiation monitoring system using Geiger–Muller tube detector and microcontroller. The radiation detector, battery, signal processing circuits, and the microcontroller board are housed inside a tabletop wooden model with an analog watch and a digital display of radiation dose rate. The alarm level has been set at 1 μSv/h and indicated through buzzer and LED. The system has been calibrated using 137Cs standard source and has a sensitivity of 0.7364 cps/μSv/h. This model can be displayed on any table/desk or kept near a doorway to continuously monitor background radiation level, without drawing public attention, to detect any movement or presence of radiation source.","PeriodicalId":32488,"journal":{"name":"Radiation Protection and Environment","volume":"44 1","pages":"19 - 21"},"PeriodicalIF":0.0,"publicationDate":"2021-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"45481473","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Gross alpha and gross beta radioactivity in 40 groundwater (borehole and well water) samples from Akwanga, Wamba and N/Eggon Areas of Nasarawa North District, Nasarawa State Nigeria was measured using the low background MPC2000B DP model Gross Alpha/Beta counter (ORTEC®-Protean Instrument Corporation). The values of gross alpha activity in this study were observed to be less than those of gross beta activity. The average activity values of gross alpha and gross beta obtained were 0.25 ± 0.04 Bq/L and 2.23 ± 0.09 Bq/L for Akwanga, 0.19 ± 0.03 Bq/L and 1.62 ± 0.08 Bq/L for Wamba and 0.30 ± 0.05 Bq/L and 3.00 ± 0.14 Bq/L for N/Eggon areas, respectively. The results are found to be below the World Health Organization guideline levels for drinking water quality of 0.5 Bq/L for gross alpha but 45% of the samples slightly exceeded the 1.0 Bq/L for gross beta. This implied that the groundwater in the study area is radiologically safe for consumption and may not pose any significant health hazards to humans by way of ingestion. The groundwater from the study area is also safe for drinking as the total dissolved solids average values were below the contamination limit for palatable drinking water guideline level of 1000 mg/L. However, a radionuclide-specific test and a regular monitoring program of the environment are hereby suggested.
{"title":"Gross alpha and gross beta radioactivity measurements in groundwater from Nasarawa North district Nasarawa state Nigeria","authors":"S. John, T. Akpa, R. Onoja","doi":"10.4103/rpe.RPE_24_20","DOIUrl":"https://doi.org/10.4103/rpe.RPE_24_20","url":null,"abstract":"Gross alpha and gross beta radioactivity in 40 groundwater (borehole and well water) samples from Akwanga, Wamba and N/Eggon Areas of Nasarawa North District, Nasarawa State Nigeria was measured using the low background MPC2000B DP model Gross Alpha/Beta counter (ORTEC®-Protean Instrument Corporation). The values of gross alpha activity in this study were observed to be less than those of gross beta activity. The average activity values of gross alpha and gross beta obtained were 0.25 ± 0.04 Bq/L and 2.23 ± 0.09 Bq/L for Akwanga, 0.19 ± 0.03 Bq/L and 1.62 ± 0.08 Bq/L for Wamba and 0.30 ± 0.05 Bq/L and 3.00 ± 0.14 Bq/L for N/Eggon areas, respectively. The results are found to be below the World Health Organization guideline levels for drinking water quality of 0.5 Bq/L for gross alpha but 45% of the samples slightly exceeded the 1.0 Bq/L for gross beta. This implied that the groundwater in the study area is radiologically safe for consumption and may not pose any significant health hazards to humans by way of ingestion. The groundwater from the study area is also safe for drinking as the total dissolved solids average values were below the contamination limit for palatable drinking water guideline level of 1000 mg/L. However, a radionuclide-specific test and a regular monitoring program of the environment are hereby suggested.","PeriodicalId":32488,"journal":{"name":"Radiation Protection and Environment","volume":"44 1","pages":"3 - 11"},"PeriodicalIF":0.0,"publicationDate":"2021-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"49602553","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Low-level liquid effluents generated from Regional Centre, Board of Radiation, and Isotope Technology (BRIT), Delhi, are generally discharged to the aquatic environment after suitable treatment (delay, decay, and dilution for short-lived radionuclides) conforming the regulatory compliance as authorized by Atomic Energy Regulatory Board, Mumbai. The Regional Center, BRIT-Delhi is generating the liquid effluents containing short-lived radionuclides 99Mo (T1/2−66.7 h) and 99mTc (T1/2−6.02 h) and also long-lived radionuclide 99Tc (T1/2−2.13 × 105 years) from the production of ready to use 99mTc-radiopharmaceuticals as human injectable product. This liquid waste generated during the washing of radioactive contaminated glassware is inorganic in nature and is stored in 02 number of sump tanks (capacity 50 m3 each) for delay and decay of short-lived radionuclides. The center has also planned to produce and supply 68Ga radiopharmaceuticals in future. There is a possibility that some of these radionuclides may reach the drinking water by various natural pathways. The presence of radionuclides in the drinking water above certain level may result in radiation dose to the public through the ingestion pathways. The observance of prescribed radionuclide concentration in waste water, total activity limits, and other basic safety requirements stipulated by the regulatory body help to minimize the public radiation dose. This article is an effort to derive the annual discharge limit for gross β activity at Regional Center, BRIT-Delhi to the aquatic environment of an inland site based on the drinking water standard limits prescribed by the World Health Organization. This article also discusses the effective dose received by the actual discharge of radioactive liquid effluent from the Regional Center, BRIT-Delhi.
{"title":"Revision of discharge limit of gross beta activity to the aquatic environment based on public dose estimation: An operational study","authors":"Hukum Singh, Teena Goel, V. Kadwad, P. Mukherjee","doi":"10.4103/rpe.rpe_56_20","DOIUrl":"https://doi.org/10.4103/rpe.rpe_56_20","url":null,"abstract":"Low-level liquid effluents generated from Regional Centre, Board of Radiation, and Isotope Technology (BRIT), Delhi, are generally discharged to the aquatic environment after suitable treatment (delay, decay, and dilution for short-lived radionuclides) conforming the regulatory compliance as authorized by Atomic Energy Regulatory Board, Mumbai. The Regional Center, BRIT-Delhi is generating the liquid effluents containing short-lived radionuclides 99Mo (T1/2−66.7 h) and 99mTc (T1/2−6.02 h) and also long-lived radionuclide 99Tc (T1/2−2.13 × 105 years) from the production of ready to use 99mTc-radiopharmaceuticals as human injectable product. This liquid waste generated during the washing of radioactive contaminated glassware is inorganic in nature and is stored in 02 number of sump tanks (capacity 50 m3 each) for delay and decay of short-lived radionuclides. The center has also planned to produce and supply 68Ga radiopharmaceuticals in future. There is a possibility that some of these radionuclides may reach the drinking water by various natural pathways. The presence of radionuclides in the drinking water above certain level may result in radiation dose to the public through the ingestion pathways. The observance of prescribed radionuclide concentration in waste water, total activity limits, and other basic safety requirements stipulated by the regulatory body help to minimize the public radiation dose. This article is an effort to derive the annual discharge limit for gross β activity at Regional Center, BRIT-Delhi to the aquatic environment of an inland site based on the drinking water standard limits prescribed by the World Health Organization. This article also discusses the effective dose received by the actual discharge of radioactive liquid effluent from the Regional Center, BRIT-Delhi.","PeriodicalId":32488,"journal":{"name":"Radiation Protection and Environment","volume":"44 1","pages":"42 - 46"},"PeriodicalIF":0.0,"publicationDate":"2021-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"48741772","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"Is as low as reasonably achievable (ALARA) concept relevant to low-dose exposures?","authors":"M. Iyer","doi":"10.4103/rpe.rpe_10_21","DOIUrl":"https://doi.org/10.4103/rpe.rpe_10_21","url":null,"abstract":"","PeriodicalId":32488,"journal":{"name":"Radiation Protection and Environment","volume":"44 1","pages":"1 - 2"},"PeriodicalIF":0.0,"publicationDate":"2021-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"44172861","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Deepti Sharma, Navneet Sharma, B. Roy, M. Pathak, Vinod Kumar, H. Ojha
Traumatic wounds are the wounds that damage both the skin and the underlying tissues. Bacterial load in wounded tissue triggers elongation of the inflammation phase of wound healing. In case of excessive inflammation, the wound may undergo delayed healing that can lead to complications such as sepsis or amputation. In the present work, a hydrogel using green-synthesized silver nanoparticles (AgNPs) was synthesized and characterized in terms of homogeneity, viscosity, spreadability, excipient compatibility, etc. The hydrogels containing different percentages of AgNPs were tested for healing efficacy in full-thickness excision wound model in adult female Sprague–Dawley (SD) rats. Safety study of hydrogels was performed in SD rats as per the OECD guideline 410. The prepared hydrogels were stable for over 3 months and remain intact on parameters such as homogeneity, pH balance, good spreadability, and extrudability. Healing efficacy study showed that an increased amount of AgNPs in hydrogel enhanced wound contraction over 100% with increased tensile strength and dense aligned collagen fibers in treated wound tissues as compared to standard (silver sulfadiazine), placebo, and sham groups. Dermal toxicity studies showed that there were no signs of irritation, inflammation, and edema on the dorsum of SD rats. Besides, there was no local and systemic toxicity in hydrogel-treated groups.
{"title":"Healing efficacy and dermal toxicity of topical silver nanoparticles-loaded hydrogel in Sprague–Dawley rats","authors":"Deepti Sharma, Navneet Sharma, B. Roy, M. Pathak, Vinod Kumar, H. Ojha","doi":"10.4103/rpe.rpe_51_20","DOIUrl":"https://doi.org/10.4103/rpe.rpe_51_20","url":null,"abstract":"Traumatic wounds are the wounds that damage both the skin and the underlying tissues. Bacterial load in wounded tissue triggers elongation of the inflammation phase of wound healing. In case of excessive inflammation, the wound may undergo delayed healing that can lead to complications such as sepsis or amputation. In the present work, a hydrogel using green-synthesized silver nanoparticles (AgNPs) was synthesized and characterized in terms of homogeneity, viscosity, spreadability, excipient compatibility, etc. The hydrogels containing different percentages of AgNPs were tested for healing efficacy in full-thickness excision wound model in adult female Sprague–Dawley (SD) rats. Safety study of hydrogels was performed in SD rats as per the OECD guideline 410. The prepared hydrogels were stable for over 3 months and remain intact on parameters such as homogeneity, pH balance, good spreadability, and extrudability. Healing efficacy study showed that an increased amount of AgNPs in hydrogel enhanced wound contraction over 100% with increased tensile strength and dense aligned collagen fibers in treated wound tissues as compared to standard (silver sulfadiazine), placebo, and sham groups. Dermal toxicity studies showed that there were no signs of irritation, inflammation, and edema on the dorsum of SD rats. Besides, there was no local and systemic toxicity in hydrogel-treated groups.","PeriodicalId":32488,"journal":{"name":"Radiation Protection and Environment","volume":"44 1","pages":"34 - 41"},"PeriodicalIF":0.0,"publicationDate":"2021-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"42254089","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"I. Report on the conduct of virtual conference of IARPNC 2020 (January 21–23, 2021)","authors":"S. Murali","doi":"10.4103/rpe.rpe_12_21","DOIUrl":"https://doi.org/10.4103/rpe.rpe_12_21","url":null,"abstract":"","PeriodicalId":32488,"journal":{"name":"Radiation Protection and Environment","volume":"44 1","pages":"54 - 55"},"PeriodicalIF":0.0,"publicationDate":"2021-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"41956647","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
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