Measurements of the Proton-Induced Reaction Cross-Sections of natMo by Using the MC50 Cyclotron at the Korea Institute of Radiological and Medical Sciences

Mayeen Uddin KHANDAKER,Guinyun Kim,A.K.M. Moinul Haque Meaze,Dongchul Son,Kwangsoo Kim,Young Seok Lee 한국물리학회 2006 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.48 No.4

We measured the production cross-sections of 99mTc, 96(m+g)Tc, 95mTc, and 95gTc radioisotopes for proton-induced reactions on molybdenum by using a stacked-foil activation technique in the energy range of 10 . 30 MeV at the MC50 cyclotron of the Korea Institute of Radiological and Medical Sciences. Reactions induced on the aluminum and copper foils were used to monitor the parameters of the proton beam. The present measurements are in generally good agreement with the earlier reported data in the investigated energy region. reg_id_no

Measurements of the Proton-Induced Reaction Cross-Sections of natMo(p,xn) 94m,94g,93m,93gTc

Mayeen Uddin KHANDAKER,Guinyun Kim,Kwangsoo KIM,Young Seok LEE 한국물리학회 2007 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.50 No.I

We measured the production cross-sections of $^{\rm 94m,94g,93m,93g}$Tc radioisotopes for proton-induced reactions on natural molybdenum by using a stacked-foil technique in the energy range of 10 -- 30 MeV at the MC50 cyclotron of the Korea Institute of Radiological and Medical Sciences. The activation method and the stacked foil technique using high-resolution HPGe gamma spectrometry were applied to determine the excitation functions. The reactions induced on aluminum and copper foils were used to monitor the parameters of the proton beam. In the investigated energy region, the present results are in generally good agreement with the earlier reported data and with the evaluated data from MENDL-2P.

Experimental Study of the Production Cross-Sections for 117m,113Sn from Proton Irradiation on a natSn Target

이영석,Mayeen Uddin Khandaker,김광수,김경숙,이만우,Guinyun Kim,조영식,이영욱 한국물리학회 2008 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.53 No.2

The production cross-sections of 117m,113Sn radioisotopes for proton-induced reactions on natural tin were measured up to 40 MeV by using a stacked-foil activation technique at the MC50 cyclotron of the Korea Institute of Radiological and Medical Sciences. The thick target integral yields were also deduced for each radionuclide by using the measured cross-sections from the respective threshold up to 40 MeV. The present results are in generally good agreement with the earlier reported data and with the theoretical data calculated by using the computer codes TALYS and ALICE-IPPE. The production yield of 117mSn from a natural tin target at a 39 MeV proton energy was 3.15 MBq/μA-h (85.14 μCi/μA-h), but the impurity level due to the long-lived 113Sn radionuclide was found to be ∽4 %. The production cross-sections of 117m,113Sn radioisotopes for proton-induced reactions on natural tin were measured up to 40 MeV by using a stacked-foil activation technique at the MC50 cyclotron of the Korea Institute of Radiological and Medical Sciences. The thick target integral yields were also deduced for each radionuclide by using the measured cross-sections from the respective threshold up to 40 MeV. The present results are in generally good agreement with the earlier reported data and with the theoretical data calculated by using the computer codes TALYS and ALICE-IPPE. The production yield of 117mSn from a natural tin target at a 39 MeV proton energy was 3.15 MBq/μA-h (85.14 μCi/μA-h), but the impurity level due to the long-lived 113Sn radionuclide was found to be ∽4 %.

A comparative study on the impact of Gd₂O₃ burnable neutron absorber in UO₂ and (U, Th)O₂ fuels

Uguru, Edwin Humphrey,Sani, S.F.Abdul,Khandaker, Mayeen Uddin,Rabir, Mohamad Hairie,Karim, Julia Abdul Korean Nuclear Society 2020 Nuclear Engineering and Technology Vol.52 No.6

The performance of gadolinium burnable absorber (GdBA) for reactivity control in UO₂ and (U, Th)O₂ fuels and its impact on spent fuel characteristics was performed. Five fuel assemblies: one without GdBA fuel rod and four each containing 16, 24, 34 and 44 GdBA fuel rods in both fuels were investigated. Reactivity swing in all the FAs with GdBA rods in UO₂ fuel was higher than their counterparts with similar GdBA fuel rods in (U, Th)O₂ fuel. The excess reactivity in all FAs with (U, Th)O₂ fuel was higher than UO₂ fuel. At the end of single discharge burn-up (~ 49.64 GWd/tHM), the excess reactivity of (U, Th) O₂ fuel remained positive (16,000 pcm) while UO₂ fuel shows a negative value (-6,000 pcm), which suggest a longer discharge burn-up in (U, Th)O₂ fuel. The concentration of plutonium isotopes and minor actinides were significantly higher in UO₂ fuel than in (U, Th)O₂ fuel except for ²³⁶Np. However, the concentration of non-actinides (gadolinium and iodine isotopes) except for ¹³⁵Xe were respectively smaller in (U, Th)O₂ fuel than in UO₂ fuel but may be two times higher in (U, Th)O₂ fuel due to its potential longer discharge burn-up.

Radiological hazards assessment associated with granitoid rocks in Egypt

Abdel Gawad Ahmed E.,Masoud Masoud S.,Khandaker Mayeen Uddin,Hanfi Mohamed Y. 한국원자력학회 2024 Nuclear Engineering and Technology Vol.56 No.6

The present study aimed to assess the radioactive hazards associated with the application of granitoid rocks in building materials. An HPGe spectrometer was used to detect the levels of the radioactive elements uranium-238, thorium-232, and potassium-40 in the granitoid rocks. The results showed that the levels of these elements were lower (38.32 < 33 Bq kg 1), comparable (47.19–45 Bq kg-1) and higher (992.26 ≫> 412 Bq kg 1) than the worldwide limits for 238U, 232Th, and 40K concentration, respectively. The exposure to gamma radiation of granitoid rocks was studied by various radiological hazard variables like the absorbed dose rate (Dair), the outdoor and indoor annual effective dose (AEDout and AEDin), and excess lifetime cancer risk (ELCR). A variety of statistical methods, including Pearson correlation, principal component analysis (PCA), and hierarchical cluster analysis (HCA) was used, to study the relationship between the radioactive elements and the radiological hazards. According to statistical analysis, the main radioactive risk of granitoid rocks is contributed to by the elements uranium-238, thorium-232, and potassium-40. Granitoid rocks can be applied in building materials, but under control to prevent risk to the public.

The radioactivity levels and beta dose rate assessment from dental ceramic materials in Egypt

Hasabelnaby Mohamed,Hanfi Mohamed Y.,El-Gamal Hany,El Gindy Ahmed H.,Khandaker Mayeen Uddin,Salaheldin Ghada 한국원자력학회 2024 Nuclear Engineering and Technology Vol.56 No.9

There is a lack of available data on the radioactivity levels of these materials, despite the potential risks they may pose to patients, dental technicians, and dentists. A total of forty samples were collected from different dental markets in Egypt. Using an NaI(Tl) detector, the gamma-ray spectrometer measured the activity levels of uranium-238, radium-226, thorium-232, and potassium-40. The findings revealed that the mean concentration of 238U (below the minimum detectable activity, MDA), 226Ra (135 ± 5 and 132 ± 5 Bq/kg), 232Th (187 ± 4 and 243 ± 8 Bq/kg), and 40K (1560 ± 52 and 2501 ± 89 Bq/kg) in feldspar and zirconia (ZrO2) dental ceramic samples, respectively, were all within the limits established by the International Organization for Standardization (ISO) and the European Commission (EC). The use of feldspar and zirconia dental ceramics to restore all teeth would result in an estimated maximum beta dose of 1.5 mGy/year to the oral tissue. The results suggest that there is no cause for concern regarding any additional beta dose to the oral cavity from the use of feldspar and zirconia dental ceramics.

Natural radioactivity, mineralogy and hazard assessment of syenogranites (ornamental stones) using a statistical approach

Taalab Sherif A.,Ismail Ahmed M.,El Maadawy W.M.,Abdelrahman Kamal,Khandaker Mayeen Uddin,Sakr Ahmed K.,Hanfi Mohamed Y. 한국원자력학회 2024 Nuclear Engineering and Technology Vol.56 No.10

The study focused on syenogranite and its altered variety, and specifically monitored the activities of 226Ra, 232Th, and 40K using NaI(Tl) gamma-ray spectroscopy. Syenogranites in the study area in Egypt were investigated to determine their potential use in industries such as ornamental stones and ceramics. The main outcrops in the study area consist of metasediments, metavolcanics, metagabbro, syn-to late-orogenic granites, and postorogenic granites (syenogranites). There are also numerous dikes and veins of various shapes and compositions that have intruded and penetrated all the older rocks in the area. The mean activity (± standard deviation, SD) of these radioelements in the granites is 226Ra (63 ± 71 Bq kg 1), 232Th (76 ± 170 Bq kg 1), and 40K (1248 ± 532 Bq kg 1) were found to be greater than the world average. The radiological hazards are mostly attributed to the γ-rays emitted by granitic rocks. The granites studied in this study deviate from international standards mainly due to the presence of minerals containing radioelements such as zircon, allanite, monazite, sphene titanite, apatite, thorite, samarskite, fergusonite, xenotime, columbite, apatite and fluorite. As a result, granitic rocks are unsuitable for home building

Assessment of radionuclides from coal-fired brick kilns on the outskirts of Dhaka city and the consequent hazards on human health and the environment

Siraz M.M. Mahfuz,Rakib M.D.A.,Alam M.S.,Al Mahmud Jubair,Rashid Md Bazlar,Khandaker Mayeen Uddin,Islam Md. Shafiqul,Yeasmin S. 한국원자력학회 2023 Nuclear Engineering and Technology Vol.55 No.8

In a first-of-its-kind study, terrestrial radionuclide concentrations were measured in 35 topsoil samples from the outskirts of Dhaka using HPGe gamma-ray spectrometry to assess the radiological consequences of such a vast number of brick kilns on the plant workers, general as well as dwelling environment. The range of activity concentrations of 226Ra, 232Th, and 40K is found at 19 ± 3.04 to 38 ± 4.94, 39 ± 5.85 to 57 ± 7.41, and (430 ± 51.60 to 570 ± 68.40) Bq/kg, respectively. 232Th and 40K concentrations were higher than the global averages. Bottom ash deposition in lowlands, fly ash buildup in soils, and the fallout of micro-particles are all probable causes of the elevated radioactivity levels. 137Cs was found in the sample, which indicates the migration of 137Cs from nuclear accidents or nuclear fallout, or the contamination of feed coal. Although the effective dose received by the general public was below the recommended dose limit but, most estimates of hazard parameters surpass their respective population weighted global averages, indicating that brick kiln workers and nearby residents are not safe due to prolonged exposures to terrestrial radiation. In addition, the soil around sampling sites is found to be unsuitable for agricultural purposes.

The status of NORMs in natural environment adjacent to the Rooppur nuclear power plant of Bangladesh

Md Abu Haydar,Md Mehade Hasan,Imrose Jahan,Kanij Fatema,Md Idris Ali,Debasish Paul,Mayeen Uddin Khandaker 한국원자력학회 2021 Nuclear Engineering and Technology Vol.53 No.12

The Rooppur Nuclear Power Plant (RNPP), the first nuclear power plant in Bangladesh with a capacity of2.4 GWe, is under construction on the bank of the river Padma, at Rooppur in Bangladesh. Measurementof background radioactivity in the natural environment adjacent to RNPP finds great importance forfuture perspectives. Soil and sediment samples collected from upstream and downstream positions ofthe Padma River (adjacent to RNPP) were collected and analyzed by HPGe gamma-ray spectrometry forprimordial radionuclides. The average activity concentrations (in Bqkg 1) of 226Ra, 232Th and 40K radionuclides in soil samples were found to be 44.99 ± 3.89, 66.28 ± 6.55 and 553 ± 82.17 respectively. Respective values in sediment samples were found to be 44.59 ± 4.58, 67.64 ± 7.93, 782 ± 108. Relevantradiation hazard indices and dosimetric parameters were calculated and compared with the worldaverage data recommended by US-EPA. Analytical results show non-negligible radiation hazards to thesurrounding populace. Measured data will be useful to monitor any change of background radioactivityin the surrounding environment of RNPP following its operation for the generation of nuclear energ

Measurements of the Neutron Total Cross-Sections of Tantalum by Using Pulsed Neutrons Based on an Electron Linac

A.K.M. Moinul Haque MEAZE,김귀년,손동철,강행식,고인수,K. DEVAN,유건중,Mayeen Uddin KHANDAKER,조무현,남궁원,이영석,김영애,이영욱 한국물리학회 2006 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.48 No.4

The neutron total cross-sections of tantalum (181Ta) were measured in the neutron energy region from 0.01 eV to 100 eV by using the time-of-flight method at the Pohang Neutron Facility, which consists of an electron linac, a water-cooled tantalum target with a water moderator, and a 12-mlong time-of-flight path. A 6Li-ZnS(Ag) scintillator with a diameter of 12.5 cm and a thickness of 1.6 cm was used as a neutron detector, and a natural tantalum metal plate, 10 × 10 cm2 in area by 0.45 mm in thickness, was used for the neutron transmission measurement. The background level was determined by using a notch-filter of Co, In, and Cd sheets. The present measurement was compared with the previous ones and the evaluated data in ENDF/B-VI.8. The resonance parameters of 181Ta isotope were obtained from the transmission ratio by using the SAMMY code, which utilizes both Doppler and resolution broadening effects and Bayes’ generalized least squares technique.