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Cross sections of the 86Sr(p,3n)84mY, 86Sr(p,αn)82mRb, and 86Sr(p,x)85gSr reactions were measured from their respective thresholds up to 16.2 MeV and from 23.0 to 44.1 MeV at FZJ, and from 14.3 to 24.5 MeV at LBNL, using 96.4% enriched 86SrCO3 as target material. Thin targets prepared by sedimentation were irradiated with protons in a stacked-form, and the induced radioactivity was measured by high-resolution γ-ray spectrometry. Nuclear model calculations based on the code TALYS reproduced our experimental cross section data well. From the excitation functions, the integral yields of the above three radionuclides were calculated. The yield of 85gSr via the natSr(n,γ) process was also measured using the TRIGA Mark-II reactor at AERE, Savar. A comparison of the reactor and cyclotron production of carrier-added 85gSr is given. The production possibilities of the three investigated radionuclides in no-carrier-added forms at a 30 MeV cyclotron via new routes are discussed.

Over the last several decades, our research group has been working on nuclear data measurements using a J-25 Neutron Generator, a TRIGA Mark II Research Reactor and a Tandem Accelerator at Savar, as well as an Am/Be neutron source at Rajshahi. The spectrum of fast neutrons having energies from 0.5 to 20 MeV in the core of the TRIGA reactor as well as from 1.5 to 11 MeV of the Am/Be source was well characterized for validation of evaluated data of neutron threshold reactions. Spectrum-averaged cross sections were determined by integral measurements. The integral values measured at both the reactor and the Am/Be source were compared with the integrated data deduced from measured and evaluated excitation functions of some nuclear reactions given in some data libraries. As example, the details on the integral and integrated cross sections of the 64Zn(n,p)64Cu and 60Ni(n,p)60Co reactions are discussed. In both cases, integral test shows that further improvement of the evaluated excitation function reported in data libraries is needed. The use of a newly developed facility at the 3 MV Tandem Accelerator in measurement of proton induced reaction cross sections in the energy region below 5 MeV is outlined, and new results on the 64Ni(p,n)64Cu and natNi(p,x)61Cu processes below 3 MeV are discussed.

The cross sections of the reactions 70Zn(n,2n)69mZn,74Ge(n,α)71mZn and 90Zr(n,2n)89m,gZr in the energy range of 13.82–14.71 MeV were measured by the activation technique in combination with HPGe detector γ-ray spectroscopy. The measured results were compared with other experimental data and with the data given in the library TENDL-2019. A nuclear model calculation based on the code TALYS-1.8 was also performed after adjustment of an input parameter for the spin distribution of level density. The results of this work strengthen the database and could be useful in further evaluation of the data.

In view of several significant discrepancies in the excitation function of the 86Sr(p,n)86g+xmY reaction which is the method of choice for the production of the non-standard positron emitter 86Y for theranostic application, we carried out a careful measurement of the cross sections of this reaction from its threshold up to 16.2 MeV at Forschungszentrum Jülich (FZJ) and from 14.3 to 24.5 MeV at LBNL. Thin samples of 96.4% enriched 86SrCO3 were prepared by sedimentation and, after irradiation with protons in a stacked-form, the induced radioactivity was measured by high-resolution γ-ray spectrometry. The projectile flux was determined by using the monitor reactions natCu(p,xn)62,63,65Zn and natTi(p,x)48V, and the calculated proton energy for each sample was verified by considering the ratios of two reaction products of different thresholds. The experimental cross section data obtained agreed well with the results of a nuclear model calculation based on the code TALYS. From the cross section data, the integral yield of 86Y was calculated. Over the optimum production energy range Ep = 14 → 7 MeV the yield of 86Y amounts to 291 MBq/μA for 1 h irradiation time. This value is appreciably lower than the previous literature values calculated from measured and evaluated excitation functions. It is, however, more compatible with the experimental yields of 86Y obtained in clinical scale production runs. The levels of the isotopic impurities 87mY, 87gY, and 88Y were also estimated and found to be

The β+- emitting radionuclide 86gY (t1/2 = 14.7 h) forms a matched-pair with the β--emitting therapeutic radionuclide 90Y (t1/2 = 2.7 d) for theranostic application in medicine. Precise knowledge of the positron emission probability of the PET nuclide is very important, which was rather uncertain for 86gY until recently. In this work, an 86gY source of high radionuclidic purity was prepared and the positron emission intensity per 100 decay of the parent (hereafter “positron emission intensity”) was determined by measuring the 511 keV annihilation γ-ray using high-resolution HPGe detector. The total source activity was obtained from known γ-ray emission probabilities. The electron capture (EC) intensity was also determined as an additional check by measuring the Kα and Kβ X-rays of energies 14.1 and 15.8 keV, respectively, using a low energy HPGe detector. From those measurements, normalized values of 27.2 ± 2.0% for β+ -emission and 72.8 ± 2.0% for EC were deduced. These results are in excellent agreement with values recently reported in the literature based on a detailed decay scheme study.

The β

Integral cross sections of the reactions 24Mg(n,p)24Na, 27Al(n,p)27Mg, 27Al(n,α)24Na, 58Ni(n,d + np)57Co and 60Ni(n,p)60Co were measured for the first time using the fast neutron spectrum of a TRIGA reactor extending from 0.5 to 20 MeV. The values obtained in this work were comparable with the recommended values for a pure 235U prompt fission spectrum. The measured integral value was utilized for integral test of excitation function of each reaction given in some data libraries, namely ENDF/B-VIII.0, TENDL-2017, IRDFF-1.05 and ROSFOND-2010. The integral measurements are generally consistent with the integrated values within 5 %, except for a few cases, e. g. the reaction 60Ni(n,p)60Co, where the data libraries appear to need improvement.

Excitation functions of the reactions 27Al(d,αp)24Na, 27Al(d,2p)27Mg and 27Al(d,p)28Al were measured by the activation technique up to deuteron energies of 37 MeV. The available experimental databases of the reaction products 27Mg and 28Al were extended and compared with the nuclear model calculations based on the code TALYS-1.8. Our measured data are reproduced well by the model calculations after adjustment of a few free input parameters. The cross-section ratio of the (d,αp) to (d,2p) process as a function of projectile energy was deduced from the measured data, and the result is interpreted in terms of competition between a proton and an α-particle emission.

Activation cross sections of application related Cd-107 and Cd-109 via proton, deuteron, alpha particle induced reactions on palladium, He-3 and alpha particle induced nuclear reactions on silver and deuteron induced reactions on cadmium and indium were measured by using the stacked foil irradiation technique and gamma-ray spectrometry. The cross sections were compared with the earlier experimental data and theoretical predictions. Integral yields were deduced on the basis of experimental data. Different production routes for both radioisotopes are compared.

Excitation functions of the natPd(p,2pxn)102m,g;101m,g;99m,gRh reactions and the cross section ratios for the isomeric pairs 102m,gRh, 101m,gRh and 99m,gRh have been measured up to 42.61 MeV. The experiments were carried out using a stacked-foil activation technique. The proton beam intensity was determined based on the natCu(p,xn)62Zn and natCu(p,xn)65Zn monitoring reactions. The activities of the irradiated palladium and cooper monitor foils were measured using a HPGe γ-ray detector. The present experimental cross sections are compared with reference data and with the theoretical predictions from TENDL-2015 libraries. The cross sections for the nuclear reactions natPd(p,2pxn)102m,gRh were measured in the energy range of 20–40 MeV and the cross section ratios for all three isomeric pairs 102m,gRh, 101m,gRh and 99m,gRh produced in the natPd(p,2pxn) reactions are the first measurements.

The excitation functions of 93Nb(p,x) reactions from their respective thresholds to 42.5 MeV were measured at the MC-50 cyclotron of Korea Institute of Radiological and Medical Sciences by using the stacked-foil activation and off-line γ-ray spectrometric technique. The thick target integral yields for the formation of the investigated radionuclides from the respective thresholds to 42.5 MeV were deduced based on the measured cross sections data. The 93Nb(p,x) reactions cross sections obtained in the present work were compared with the literature data and theoretical values based on the TENDL-2015 data library. The production cross sections of the investigated radionuclides (e.g. 88,89Zr, 87,88Y, 90Nb) are applicable in research, medical diagnosis and radiotherapy. The present data provide information’s, which will support in testing and understanding the nuclear reaction models.

Excitation functions of the natNi(α,x)60,61Cu and 64Ni(α,p)67Cu reactions were measured using the stacked-foil activation technique. The experimental data achieved were compared with literature data as well as with nuclear model calculations performed using the code TALYS-1.8. Integral yields from the respective thresholds to 44 MeV were deduced from the measured excitation curves. The >99% pure 61Cu can be produced using the energy window of Eα=20→7 MeV, the yield amounting to 116 MBq/μAh. After a 2 h cooling time, the short-lived 60Cu (T1/2=23 min) impurity will be reduced to 64Ni, the enriched 64Ni target would be needed for the production of 67Cu via the (α,p) reaction. The cost would, however, be very high. In a few cases, particularly above 24 MeV, we have given new data points. In general, our measurements have strengthened the database.

Excitation functions for the formation of the radionuclides 56Co, 57Co, 58m+gCo and 54Mn via proton induced reactions on natural iron target were measured from their respective thresholds up to 16 MeV using the stacked-foil activation technique and HPGe detector γ-ray spectroscopy. In the threshold energy range, the low cross sections for 54Mn were measured radiochemically. All the measured values were compared with available experimental data and with theoretical calculations reproduced in TENDL-2015 nuclear data library. New data for the formation of 57Co, 58Co and 54Mn were obtained near their reaction thresholds. Other data obtained strengthen the database. Polynomial fittings of the data measured in this work as well as of all data sets (including the present data) were performed. The present data appear to be closer to theoretical calculations than the literature data.

Precise identification and quantification of radioisotope in a sample largely depend on the accuracy of the full-energy peak efficiency of the detector. It is generally observed that the efficiency for a given energy of point-like sources is not the same as the extended source. However, number of correction factors such as detector geometry, photon attenuation, coincidence-summing, etc. may reduce such a difference in efficiency regardless of sources, or they should be considered in the measurement of extended samples. In connection to this, the variation of absolute photopeak efficiency of a high-purity germanium (HPGe) detector with the distances from the surface of the detector as well as with the $$\upgamma $$ -ray energies were investigated using $$\upgamma $$ -ray standard point sources. We present a method to determine the loss of efficiencies in radioactivity measurement of the thin extended radioactive disc samples in comparison to point source.

Noise has always been a major disturbance for every living creature. Noise pollution is, thus, a threat to environmental pollution too. The noise created by a helicopter draws a great contribution to the noise pollution. Reducing the noise that creates from helicopter rotor blades, tail rotors, engine etc. is a one step closer to this crisis. Helicopter noise reduction is a topic of research into designing helicopters which can be operated more quietly. The major source of the noise come from the rotor blade vortex interaction. By attaching spoiler in the helicopter main rotor blades and tail rotors reduce the noise and silence the operation. The spoiler is made of supple, resilient, and durable non-ferrous material, such as rubber, a rubber like material, plastic, rubber-impregnated with thin steel mesh, canvas reinforced rubber, rubber composites, and other durable materials that do not prematurely fatigue. The spoiler attached at the trailing edges of blades have free edges exhibits a non-repeating pattern of feather-like projections that collectively break up the vortex formed by blade rotation by providing clean air for each successive blade. The blade efficiency is also increased by using spoiler. This paper addresses the use of spoiler and comparison of noise level of rotor blades with or without spoiler.

This paper presents the feasibility of using solar photovoltaics (Solar PV) as the energy source for cooking with special focus on the loss mechanisms and possible remedial measures. If the heat loss is minimized, to reduce the temperature losses, it is possible to cook with a low power source less than 500 W. A slogan has been adopted by the researchers&mdash, &lsquo, It is temperature that cooks food not heat&rsquo, meaning that it is not the flow of energy that cooks food, but rather, that food is cooked when held at a key temperature for a time. The slogan draws attention to the core concept that if heat loss is minimized, maintaining the temperature inside the cooker and the cooking pan, then the cooking process becomes very energy efficient. The paper considers ways to maintain temperature, but with due reference to the &lsquo, art of cooking&rsquo, those all-important cultural processes that determine how meals are made. A prototype solar home system e-cooker was designed, fabricated and tested for cooking different foods in Bangladesh. Experimental results are presented to show that cooking is possible using much less power and energy than is commonly thought. A cost analysis is also presented to show that such a cooker can be cost effective in off-grid areas if connected to a properly designed Solar Home System.

Excitation functions of the natFe(\( \alpha\), x)57Ni, natFe(\(\alpha\), x)55, 56, 57, 58m, gCo and natFe(\(\alpha\), x)52, 54Mn reactions were measured using the stacked-foil activation technique. The induced radioactivities in both the target and monitor foils were measured using an off-line \(\gamma\)-ray spectrometric technique. The cross sections for the above reactions were also calculated theoretically using the TALYS-1.8 code. The measured results were compared with the other experimental data and theoretical values. The theoretically calculated values are described well by our experimental data. It is observed that the rate of proton emission is larger than the neutron one. The measured results for the formation of few radionuclides are new and the other measured data strengthen the database. The experimental and theoretical studies on the investigated reactions should lead to a useful insight into the mechanisms of those reactions.

The cross sections of the reaction 98Mo(n, γ)99Mo at neutron energies of 0.0334 eV and 0.0536 eV were measured for the first time using the activation technique, and the resulting values of 116 ± 7 mb and 91 ± 5 mb, respectively, are in good agreement with the JENDL-4 and ENDF/B-VII data files. Those measured values were extrapolated to the energy 0.0253 eV assuming 1/v dependence in the thermal region and the results were compared with the integrally measured values reported in the literature. The new data are thus useful to check the evaluated excitation function.

Excitation functions of the natNi( $\alpha$ ,x)62,63,65Zn, natNi( $\alpha$ ,x)56,57Ni and natNi( $\alpha$ ,x)56,57,58m+gCo reactions were measured from the respective thresholds to 44MeV using the stacked-foil activation technique. The tests for the beam characterization are described. The radioactivity was measured using HPGe $\gamma$ -ray detectors. Theoretical calculations on $\alpha$ -particles-induced reactions on natNi were performed using the nuclear model code TALYS-1.8. A few results are new, the others strengthen the database. Our experimental data were compared with results of nuclear model calculations and described the reaction mechanism.

An analysis of metallic elements and natural radioactivity in soils collected from two shipyards and their surroundings in Chittagong, Bangladesh is presented. The elemental concentrations of the metals Cr, Mn, Fe, Ni and Cu were obtained by PIXE analysis with a 3 MV Tandem Accelerator, and the radioactivity of 226Ra, 232Th and 40K was determined using HPGe gamma-ray spectrometry. From the mean specific activities of the three radionuclides in soil samples, the radium equivalent activity, the gamma absorbed dose rate, the annual effective dose rate and the external hazard index were calculated. The study was focused on investigation of soil contamination via shipbreaking activities, if any. The somewhat higher contents of Cr, Mn, Fe, Ni and Cu in soil samples of shipyards, as compared to other locations, seem to be caused by the shipbreaking activities. The specific radioactivities as well as radium equivalent activity in soils of shipyards are also higher and thus possibly an indirect result of shipbreaking activities.

The neutron capture cross section for the 152Sm(n, γ)153Sm reaction at an energy of 0.0334 eV was measured for the first time using monochromatic neutrons of a powder diffractometer at the TRIGA Mark II nuclear reactor at Dhaka, Bangladesh. The 197Au(n, γ)198Au reaction was used to monitor the neutron beam intensity. The radioactivity of the products was determined via high resolution γ-ray spectrometry. The obtained cross section value is 184 ± 22 b, which is consistent with both the ENDF/B-VII and TENDL-2012 data libraries. The measured value at 0.0334 eV and the previous data at 0.0536 eV confirm the reliability of the data in the above libraries.

Integral cross sections of the 64Zn(n, p)64Cu and 67Zn(n, p)67Cu reactions were measured for the fast neutron spectrum of TRIGA Mark-II reactor at Savar, Dhaka, Bangladesh. A clean radiochemical separation was performed to isolate the copper radionuclides from the target element zinc. The radioactivities produced in the irradiation were measured by HPGe γ-ray spectroscopy. The neutron flux over the energy range 0.5–20 MeV was determined using the 58Ni(n, p)58Co monitor reaction. The measured results amount to 28.9 ± 2.0 mb and 0.84 ± 0.07 mb for the formation of 64Cu and 67Cu, respectively. These values are slightly lower than the respective values for a pure fission spectrum. The present results were compared with data calculated using the neutron spectral distribution and the recently critically analysed excitation function of each reaction given in the literature. The good agreement validates the reliability of those excitation functions. The feasibility of simultaneous production of 64Cu and 67Cu with fast neutrons is discussed.

The neutron spectrum in the energy range of 0.1 to 5.85 MeV in the 0○ direction with respect to the incident proton beam accelerated in a Tandem Accelerator of the Wakasa Wan Energy Research Center (WERC), Japan, has been characterized using the multiple foil activation technique. Flux mapping of thermal and epithermal neutrons at 0○, 20○, 40○ and 60○ at downstream of the beam has also been carried out. The fast neutron spectrum averaged cross sections of several threshold reactions were measured. Two monitor reactions, 58Ni(n, p)58Co and 115In(n, n′, γ)115mIn, were used to determine the fast neutron flux. The use of fast neutron flux in validating some excitation functions is described.

Integral cross sections of the reactions 24Mg(n,p)24Na, 27Al(n,p)27Mg, 27Al(n,α)24Na and 95Mo(n,p)95Nb were measured for the first time with fast neutrons (E n > 1.5 MeV) from an Am/Be source. Furthermore, upper cross section limits for the reactions 98Mo(n,α)95Zr and 103Rh(n,p)103Ru were deduced. The results were compared with data calculated using the neutron spectral distribution and the excitation function of each reaction given in the data files and libraries ENDF/B-VII, JEFF-3.1.2, JENDL-4.0, IRDF-2004, TENDL-2010, ROSFOND-2010 and CENDL-3.1. In general, the integral measurement and the integrated value agreed within ± 10%. The fast neutron field (with E n > 1.5 MeV) of the Am/Be source is thus well suited for integral tests of excitation functions of neutron threshold reactions.

Activation of thin electrodeposited natural Os targets was investigated in a stacked foil irradiation with a 50 MeV deuteron beam. Assessments of the produced radionuclides by high resolution gamma spectroscopy yielded excitation functions for production of 184,185,186m1,g,187m1+g,188m1+g,189m2+m1+g,190m2,190m2,m1+g,192m1+g Ir and 185 Os. Reduced uncertainty on cross sections is obtained by simultaneous remeasurement of the 27 Al(d,x) 24 Na monitor reaction over the whole energy range. Thick target yield for deuteron induced production route of 192m1+g Ir and comparison with the nat Ir(n,γ) route are reviewed. A comparison with updated theoretical codes (ALICE-D, EMPIRE-D and the TENDL2011 on-line library) is discussed.

Activation cross sections of proton induced nuclear reactions on palladium were measured up to 80 MeV by using the stacked foil irradiation technique and gamma ray spectrometry. The beam intensity, the incident energy and the energy degradation were controlled by a method based on flux constancy via normalization to the excitation functions of monitor reactions measured in parallel. Excitation functions for direct and cumulative cross-sections were measured for the production of Ag-104 m,Ag-104 g,Ag-105 g,Ag-106 m,Ag-110 m, (PdRh)-Pd-100,101-Rh-, 99 m,99 g,100,101 m,101 g,102 m,102 g,105 and Ru-103,Ru-97 radioisotopes. The cross section data were compared with the theoretical predictions of TENDL-2014 and -2015 libraries. For practical applications thick target yields were derived from the measured excitation functions. Application in the field of medical radionuclide production is shortly discussed. (C) 2016 Elsevier Ltd. All rights reserved.

Excitation function of the reaction $^{60}\mathrm{Ni}(p,\ensuremath{\gamma})^{61}\mathrm{Cu}$ was measured via the activation technique in the energy range of 1.3--16.0 MeV using a low-energy accelerator and a small cyclotron. The results are comparable to those previously obtained via prompt \ensuremath{\gamma} counting. In addition excitation functions of the more common competing $^{60}\mathrm{Ni}(p,n)^{60}\mathrm{Cu}$ and $^{60}\mathrm{Ni}(p,\ensuremath{\alpha})^{57}\mathrm{Co}$ reactions were also measured. Theoretical calculations on proton-induced reactions on $^{60}\mathrm{Ni}$ were performed using the nuclear model code talys. The results suggest that near the threshold of the reaction the compound nucleus mechanism dominates. Thereafter the contribution of direct interactions becomes rather strong, especially between 4 and 6 MeV, i.e., just below the threshold of the $^{60}\mathrm{Ni}(p,n)^{60}\mathrm{Cu}$ reaction. The cross section at the maximum of the excitation function of each of the three reactions, namely, $^{60}\mathrm{Ni}(p,\ensuremath{\gamma})^{61}\mathrm{Cu},^{60}\mathrm{Ni}(p,n)^{60}\mathrm{Cu}$, and $^{60}\mathrm{Ni}(p,\ensuremath{\alpha})^{57}\mathrm{Co}$, amounts to 2, 320, and 85 mb, respectively. The $(p,n)$ reaction is thus the most commonly occurring process, and the $(p,\ensuremath{\gamma})$ reaction is the weakest, possibly due to higher probability of particle emission than \ensuremath{\gamma}-ray emission from the highly excited intermediate nucleus $^{61}\mathrm{Cu}$ formed in the interaction of a proton with the target nucleus $^{60}\mathrm{Ni}$.

In order to improve the quality of deuteron-induced activation data required for the safety design of the IFMIF (International Fusion Materials Irradiation Facility), we have measured (1) the activation cross-section of natLi(d,x)7Be in the deuteron-energy range from 7 to 39 MeV and (2) the production rates of radioactive nuclides in thick targets for natLi(d,x)7Be, natC(d,x)7Be, and 27Al(d,x)7Be, 22Na, 24Na reactions at 40 MeV using the AVF cyclotron of Tohoku University. We have also estimated the production rates of these nuclides in the thick targets below 40 MeV using the cross-sections obtained in this study. The present data compared favorably with other experimental data, IAEA-recommended data, and the data obtained using the recent nuclear reaction code TALYS and the activation code IRACM, which is based on the ALICE-F code. Some calculation results showed marked disagreement with the experimental data.

The neutron capture cross section for the 139 La(n, γ) 140 La reaction at 0.0536 eV was measured for the first time using monochromatic neutrons coming from a Triple Axis Spectrometer at the TRIGA Mark-II reactor. The neutron beam intensity was determined by irradiating Au-monitor foil together La 2 O 3 target. The radioactivity of the products was determined via high resolution γ-ray spectrometry. The obtained cross section value is 6.13±0.3b, which is 1.34% and 0.21 % lower than that in the ENDF/B-VII and JENDL-3.3 data library, respectively.

Production cross-sections of (103)Ag obtained by irradiating (nat)Pd and (nat)Cd with 70 MeV protons are presented and compared with ALICE-IPPE model calculations. Production of (103)Ag is of interest for the generation of (103)Pd widely used in brachytherapy. The investigated energy range of the (103)Rh(d,2n)(103)Pd reaction was extended up to 40 MeV and the results were compared with the curves of ALICE-IPPE, EMPIRE-II and GNASH theoretical codes. Thick target yields were calculated. An overview and analysis of the most important charged particle induced production routes of (103)Pd is presented. An explanation of the apparent discrepancy in the activity measurements for (103)Rh based on X- or gamma-ray is given.

The present paper presents the measurement of neutron induced activations on concrete using the 64.5 MeV quasimonoenergetic neutrons produced at the intense 7 Li(p, n) neutron source at Cyclotron and Radioisotope Center, Tohoku Univeristy (CYRIC). The data were corrected for the effect of continuous neutrons in the source. The neutron energy, neutron yields and the spectrum of continuous neutrons were confirmed with the neutron time-of-flight method and the neutron activation measurement of the 209 Bi(n, Xn) reactions having various threshold energy values. The nuclides produced by thermalized source neutrons are negligible. New data were obtained for concrete activation.

The concentrations of arsenic (As), chromium (Cr) and iron (Fe) were determined in the foodstuffs, soils and sediments from various areas in Bangladesh and new data for these toxic trace elements were given. The arsenic pollution problems in the most of the areas of Bangladesh are of geological origin. The high level of As in foodstuffs, soils and sediments, except for tannery sediments is probably positively correlated to the Fe concentration. An excessive amount of chromium was found in the sediments from the tannery area of Bangladesh.

The excitation function of the natW(p,xn)186Re nuclear reaction was measured as a function of the proton energy in the range of 6 - 40 MeV by using a stacked-foil activation technique combined with high-purity germanium gamma-ray spectroscopy at the MC50 cyclotron of the Korea Institute of Radiological and Medical Sciences. The present results are in good agreement with the earlier reported experimental data and the theoretical calculation based on the TALYS code. The thick target integral yield was also deduced from the measured excitation function and stopping power of natW over the energy range from threshold up to 40 MeV.

We measured the production cross-sections of 86,87m,87(m+g),88Y radioisotopes for proton-induced reactions on natural zirconium by using a stacked-foil activation technique in the energy range of 4-40 MeV at the MC50 cyclotron of the Korean Institute of Radiological and Medical Sciences. The activation method and the stacked-foil technique using the high-resolution HPGe gamma spectrometry were applied to determine the production cross-sections. The beam current was determined by the monitor reactions natCu(p,x)62Zn and 27Al(p,x)22,24Na. This work reports new data for the above reactions. The results were also compared with ALICE-IPPE model calculations compiled in MENDL-2P file. This experiment is in partial agreement with model calculations. The optimum energy range for the production of 86Y is 40 – 30 MeV The highest yield of 86Y amounts to 33.37 MBq/μAh over this energy range and the levels of the 87Y, 87mY and 88Y impurities to 2.3, 26.55 and 0.33 %, respectively at EOB. The natZr(p,x) process may be ...

Activation data of lead are of great importance due to the widespread applications of this element in various technological fields and to the well known adverse effects to biological systems. Use of high sensitivity radioanalytical techniques allows study of uptake, distribution and speciation. Cross sections of deuteron induced nuclear reactions on lead were measured up to 40 MeV using the standard stacked foil irradiation technique and high resolution gamma-ray spectrometry. Experimental cross sections and derived integral yields are reported for the natPb(d,xn)203,204,205,206,207Bi, natPb(d,x)203Pb202Tl reactions. Only one set of experimental cross section data was found in the literature. The experimental data are analyzed and compared with the results of the theoretical model code ALICE-IPPE and with the experimental integral yield reported in the literature.

We measured the excitation functions for the production of the 181,182m,182g,183,184g,186Re radioisotopes from proton bombardment of natural tungsten by using a stacked-foil activation technique in the energy range from threshold energy to 40 MeV at the MC50 cyclotron of the Korea Institute of Radiological and Medical Science. The results were compared with the earlier reported experimental data and the model calculations using codes TALYS and ALICE-IPPE. The present values are in good agreement with some of the previously reported literature. The integral yields for thick targets were also deduced from the measured excitation functions of the produced radioisotopes. The deduced yield values were compared with the available directly measured thick target yield, and found acceptable agreement. The investigated radioisotope 186Re has remarkable applications in the field of nuclear medicine, whereas the data of 183,184gRe have potential applications in thin layer activation analysis.

Excitation functions of the natMo(p,xn)93m,93m+g,94mTc, natMo(p,pxn)90Mo and natMo(p,αxn)89g,89m,97Nb reactions were measured using the stacked foil activation technique up to 70 MeV. These data have been measured for the first time. The measured results were compared with the ALICE-IPPE precompound-hybrid model calculations. The calculations are in partial agreement with the measured values. Maximum production of 94mTc was found in the energy range 10–37 MeV, wherein the radionuclidic impurities for 93mTc and 93gTc are about 17% and 30%, respectively.

Excitation functions for the natZr(p,xn)90,92m,95g,96Nb, natZr(p,pxn)88,89Zr, and natZr(p,αxn)86,87m,87mg,88Y reactions were measured by using a stacked-foil activation technique in combination with HPGe γ-ray spectroscopy using the MC50 cyclotron at the Korean Institute of Radiological and Medical Sciences, Korea. In this way the proton beam energy range 4–40 MeV was covered. We report new data for these processes. The data were compared with the results of precompound-hybrid model calculations, whereby only a partial agreement was obtained.

A newly developed facility at the 3 MV Tandem Accelerator at Dhaka for measurement of proton induced reaction cross sections in the energy region below 5 MeV is outlined and tests for the beam characterization are described. The results were validated by comparison with the well-known excitation function of the 64Ni(p, n)64Cu reaction. Excitation functions of the reactions nat Ni(p, x)60,61Cu, nat Ni(p, x)55,57,58m+g Co and nat Ni(p, x)57Ni were also measured from threshold to 16 MeV using the stacked-foil technique, whereby irradiations were performed with 5 MeV protons available at the Tandem Accelerator and 16.7 MeV protons at the BC 1710 cyclotron at Jülich, Germany. The radioactivity was measured using HPGe γ-ray detectors. A few results are new, the others strengthen the database. In particular, the results of the reaction nat Ni(p, x)61Cu below 3 MeV could serve as beam monitor.

Cross-sections for the residual radionuclide productions by proton-induced activation on natural molybdenum were measured up to 40 MeV by using a stacked-foil technique at the MC50 cyclotron of the Korea Institute of Radiological and Medical Sciences (KIRAMS). This work has given a new data set for the formation of the investigated radionuclides. The present results for most of the radionuclides showed in general good agreement with the earlier reported data as well as the theoretical data taken from the calculations based on the ALICE-IPPE code. The integral yields for thick targets were also deduced from the measured cross-sections of the produced radionuclides. The optimum production of the 99m Tc radionuclide with minimum impurities can be obtained at the energy ranges from 10 to 23 MeV, where the production yields were obtained as 597.15 MBqμA −1 h −1 at saturation. The measured cross-sections are used for production of medically important radionuclides such as 99m Tc, 94m Tc and 93m,g Tc by using the medium-energy cyclotrons.

Excitation functions of proton induced reactions on Pd are important for medical radioisotope production, for activation analysis, for development of low activation materials and other purposes. No experimental data exist in the literature for low and medium energy range protons. A detailed study of the excitation functions was performed up to 80 MeV proton energy by using the stacked foil irradiation technique and gamma-ray spectrometry. The irradiations were carried out at the external beam lines of the AVF cyclotron at the Tohoku University. Japan (80 and 70 MeV) and the CGR 560 cyclotron at the Vrije Universiteit Brussels (38, 29 and 17 MeV). The beam intensity, the incident energy and the energy degradation were controlled by a method based on flux constancy via normalization to the parallel measured excitation functions of Al-nat(p,x)Na-22,Na-24 and Cu-nat(p,x)Co-56,Co-58, Zn-62,Zn-65 monitor reactions. Excitation functions for direct and cumulative cross sections have been measured for the production of Ag-105m,Ag-110m, Pd-101, Rh-101m and Ru-97 radionuclei. Calculations for the excitation functions using the Alice-IPPE code were performed with a view to estimate the weight of the different contributing reactions and to check the trend and the magnitude of the obtained experimental data.

We have measured the production cross-sections of the residual radionuclides for proton-induced reactions on natural tin by using a stacked-foil activation technique in the energy range from threshold energy to 40 MeV at the MC-50 cyclotron of the Korea Institute of Radiological and Medical Sciences. The results were compared with the earlier reported experimental data and theoretical calculations based on the TALYS and the ALICE-IPPE codes. The present results are in general good agreement with the available literature data and calculated results by using the computer codes TALYS and ALICE-IPPE. The thick target integral yields were also deduced from the measured excitation functions of the produced radionuclides.

Excitation functions were measured for the89Y(d,x)90m,88,87m,87m+gY,89Y(d,x)88,89Zr and89Y(d,x)85Sr reactions in the energy range 9–40 MeV by the stacked-foil activation technique in combination with high resolution HPGe γ-ray spectroscopy. The data above 27 MeV have been measured for the first time. Yield calculations revealed that in the deuteron-induced activation of yttrium the direct production of88Y is about two times lower than that of88Zr. The maximum cross section for the production of the PET isotope89Zr by the Y+dprocess is higher than by Y+p. The yields and decay characteristics of the88Y and88Zr nuclides are suitable for thin layer activation (TLA) analysis.

The basic parameters related to radiochemical separation of iodine from tellurium and antimony by anion-exchange chromatography using the resin Amberlyst A26 were studied. The separation yield of 124I amounted to 96% and the decontamination factor from 121Te and 122Sb was > 104. The method was applied to the production of 124I via the 123Sb(α, 3n) reaction. In an irradiation of 110 mg of natSb2O3 (thickness ∼ 0.08 g/cm2) with 38 MeV α-particles at 1.2 μA beam current for 4 h, corresponding to the beam energy range of E α = 37 → 27 MeV, the batch yield of 124I obtained was 12.42 MBq and the 125I and 126I impurities amounted to 3.8% and 0.7%, respectively. The experimental batch yield of 124I amounted to 80% of the theoretically calculated value but the level of the radionuclidic impurities were in agreement with the theoretical values. About 96% of the radioiodine was in the form of iodide and the inactive impurities (Te, Sb, Sn) were below the permissible level. Due to the relatively high level of radionuclidic impurity the 124I produced would possibly be useful only for restricted local consumption or for animal experiments.

Using the stacked-foil activation technique, cross-sections of proton induced reactions on natural Sn were determined up to 67 MeV. Excitation functions are reported for the first time for the product nuclides 109 In, 110 In, 111 In, 114m In, 113 Sn, 117m Sn, 115 Sb, 120m Sb. Comparison with low energy published data for reactions leading to 116m Sb, 117 Sb, 118m Sb, 122 Sb, 124 Sb are discussed. For all excitation functions a theoretical calculation using the ALICE-IPPE code was performed. Relevance to the production of medically relevant radioisotopes ( 111 In, 114m In, 117m Sn) is discussed.

Excitation functions of the reactions natIr(d, xn)188,189,191,193mPt and natIr(d, x)189,190g,192g,194g,194m2Ir were measured up to 40 MeV using the stacked foil technique. No earlier cross sections were found in the literature. The measured experimental data were analyzed and compared to theoretical calculations based on the model code ALICE-IPPE. Use of the experimental cross sections for practical applications is also discussed.

A systematic study on the activation cross-sections for deuteron induced reactions on platinum was carried out. In the present work the energy range covered was extended up to 40 MeV [F. Tarkanyi, S. Takacs, F. DitrOi, A. Hermanne, Yu.N. Shubin, A.I. Dityuk, Nucl, Instr. and Meth. B 226 (2004) 490] for the n a t Pt(d,x) 1 9 1 , 1 9 2 , 1 9 3 , 1 9 4 , 1 9 5 , 1 9 6 m , 1 9 6 , 1 9 8 , 1 9 9 Au, n a t Pt(d,x) 1 9 1 , 1 9 5 m , 1 9 7 Pt and n a t Pt(d,x) 1 9 2 Ir reactions by using the stacked foil irradiation technique. Calculations of the excitation functions were performed by the ALICE-IPPE code and compared with the experimental results. The possible application of the experimental data is discussed.

Excitation functions of the reactions natIr(p, xn)188,189,191Pt, natIr(p, x)185,186g,188,189,190g,192gIr and natIr(p, x)185Os were measured up to 70 MeV. The measured experimental data were compared with previously published results and analyzed using theoretical calculations based on the model code ALICE-IPPE. The new measured data show significant deviations from the earlier experimental results. Applications are also discussed.