Abstract In this study, production routes of medical 110,111 In radionuclides produced by 110 Cd(p, n) 110 In, 111 Cd(p, 2n) 110 In, 112 Cd(p, 3n) 110 In, 107 Ag(α, n) 110 In, 109 Ag(α, 3n) 110 In, 111 Cd(p, n) 111 In, 112 Cd(p, 2n) 111 In, 113 Cd(p, 3n) 111 In, 114 Cd(p, 4n) 111 In, 109 Ag(α, 2n) 111 In, 107 Ag(α, γ) 111 In and 113 In(n, 3n) 111 In reactions have been investigated up to 70 MeV incident particle energy. In these calculations, the pre-equilibrium and equilibrium effects have been investigated. The pre-equilibrium calculations involve the geometry dependent hybrid model and the cascade exciton model. The full exciton model has also been used to investigate the pre-equilibrium direct effects. Equilibrium effects are calculated according to the Weisskopf–Ewing model. The calculated results are compared with the experimental data taken from the literature.
Ozet: Optik Uyarmali Luminesans yontemi ozellikle 1985'den beri arkeolojik ve jeolojik numunelerin esdeger doz tespitinde ve tarihlendirilmesinde yogun bir sekilde kullanilmaktadir. Bu yontemde, feldspat numuneler icin en uygun uyarma dalgaboyu infrared'dir ve bu durumda islem Infrared Uyarmali Luminesans (IRSL) olarak adlandirilir. Tarihlendirme isleminin en onemli adimlarindan birisi esdeger doz (Paleodoz-Toplam doz) olcumudur. Bu calismada, icinde dogal oksijenli ortam ureten Tokat-Ballica Magarasindan alinan numunelerin esdeger doz olcumleri tek tablet ilave doz (SAAD) ve tek tablet yeniden olusturma ilave doz (SARA) yontemleri kullanilarak hesaplanmistir. Cevresel sartlarin, tarihlendirme islemlerinde onemli bir parametre oldugu sonucuna varilmistir. Anahtar kelimeler: OSL, IRSL, feldispat THE DETERMINATION OF EQUIVALENT DOSE WITH IRSL METHOD FOR UNDERWATER SAMPLES FROM TOKAT-BALLICA CAVE Abstract: Particularly since 1985, Optically Stimulated Luminescence Technique has been intensively used in determination of equivalent dose and dating of archeological and geological materials. In this method, the most suitable wavelength is infrared to stimulate the feldspar sediments, and in this case it is called Infrared Stimulated Luminescence (IRSL). One of the most important steps in dating is the measurement of equivalent dose (Paleodose). In this study, equivalent dose determination of sediment obtained from Tokat-Ballica Cave that is formed medium with natural oxygen itself is calculated using Single Aliquot Additive Dose (SAAD) and Single Aliquot Regeneration Additive Dose (SARA) processes. The conclusion is drawn that the environmental conditions is an important parameter for the determination of equivalent dose in dating. Key words: OSL, IRSL, feldspar
Carbon ions are a type of particle used in hadron therapy to destroy cancerous cells. In carbon ion therapy, high-energy carbon ions target and destroy cancer cells. However, a problem with carbon ion therapy is that high-energy carbon ions can produce secondary neutrons due to nuclear interaction with the targeted tissue. These secondary neutrons can damage surrounding healthy tissue and increase radiation exposure. This study aims to determine the effect of biomaterials used instead of the cranium in the skull on the range of carbon ion beam and secondary neutron production through PHITS Monte Carlo simulation. For this reason, polytetrafluoroethylene (PTFE), alumina (Al2O3), and Ti alloy (Ti6Al4V) biomaterials used in cranioplasty were defined in place of the cranium in a slab head phantom. The ranges of carbon ion beams with energy of 90-185 MeV/u and the secondary neutrons they produced were calculated. The biomaterial that gave results closest to the cranium at all energies was seen as polytetrafluoroethylene. The range of carbon ions with an energy of 185 MeV/u was calculated as 6.9 cm in the cranium, while it was calculated as 6.4 cm when PTFE biomaterial was placed instead of the cranium. It was observed that the range of carbon ion beams decreased by approximately 7% in PTFE compared to cranium. Secondary neutrons were calculated as 1.46 in the cranium and 1.57 in PTFE. It was observed that secondary neutron production increased by almost 8% in PTFE compared to cranium.
Our purpose is to measure the internal radiation dose (ID) using human blood sample. In the literature, there is no process that allows the direct measurement of ID received by a person. This study has shown that it is possible to determine ID in human blood exposed to internal or external ionizing radiation treatment both directly and retrospectively. OSL technique was used to measure the total dose from the blood sample. OSL counts from the waste blood of the patient injected with a radiopharmaceutical for diagnostic or treatment purposes and from a blood sample having a laboratory-injected radiation dose were both used for measurements. The decay and dose-response curves (DRC) were plotted for different doses. The doses received by different blood aliquots have been determined by interpolating the natural luminescence counts to DRC. In addition, OSL counts from a healthy blood sample exposed to an external radiation source were measured. The blood aliquots were given different 0-200Gy beta doses and their decay and dose-response curves were plotted. The internal dose received by the blood aliquots injected with radioisotope was determined by interpolating the natural luminescence counts to DRC. The internal dose values were found as 0.46Gy and 0.51Gy for different dose range. The blood aliquots were exposed to different external laboratory doses. The internal dose values corresponding to 10Gy laboratory dose from the aliquots exposed to external radiation were found as 10.94Gy for Disc3 and ~10.79Gy for Disc1.This study shows that the dose received by a person can be measured directly, simply and retrospectively by using only a very small amount of blood sample. The results will have important ramifications for the medicine and healthcare fields in particular.
An analytical formulation that calculates the thermodynamic properties of zirconium carbide and zirconium nitride has been produced using the n-dimensional Debye function. The results of the heat capacity and entropy calculated here for ZrM (M=N and C) were compared with the literature data, and are found to be in agreement. This agreement shows that the used method would be useful to calculate the thermophysical properties (heat capacity, entropy, etc.) of materials such as ZrC and ZrN.
In this study the nuclear energy level density based on nuclear collective excitation mechanism has been identified in terms of the low-lying collective level bands near the neutron binding energy. Nuclear level density parameters of some light deformed medical radionuclides used widely in medical applications have been calculated by using different collective excitation modes of observed nuclear spectra. The calculated parameters have been used successfully in estimation of the neutron-capture cross section basic data for the production of new medical radionuclides. The investigated radionuclides have been considered in the region of mass number 40<A<100. The method used in the present work assumes equidistance spacing of the collective coupled state bands of the interest radionuclides. The present calculated results have been compared with the compiled values from the literatures for s-wave neutron resonance data.
