Radionuclide Radiation Research Articles

Peptide radionuclide radiation therapy with Lutathera in multirecurrent nonanaplastic meningiomas: antitumoral activity study by growth rate analysis.

Several retrospective studies and meta-analyses of Peptide Radionuclide Radiation Therapy in meningiomas suggest six-month progression-free survival improvement for WHO grade 1 and 2 meningiomas. In the present study, we aimed to evaluate the impact of such treatment on three-dimensional volume growth rate (3DVGR) in nonanaplastic meningiomas. The authors performed a retrospective study including eight patients treated with Lutathera®. Millimetric 3D T1-weighted with gadolinium enhancement magnetic resonance imaging sequences were requested for volume measurement. Then, tumor growth rate was classified following a previously described 3DVGR classification (Graillon et al.). Patients harbored seven WHO grade 2 meningiomas and one aggressive WHO grade 1. All patients, except one, underwent four treatment cycles. 3DVGR significantly decreased at 3, 6, and 12 months after treatment initiation analyzing each lesion separately. Mean and median 3DVGR from all patients were respectively at 29.5% and 44.5%/6 months before treatment initiation, then at 16.5% and 25%/6 months at three months post-treatment initiation, 9.5% and 4.5%/6 months after 6 months, as well as 9.5% and 10.5%/6 months after 12 months. At 3, 6, and 12 months after treatment initiation, 4/8, 6/7, and 5/6 patients were class 2 (stabilization or severe 3DVGR slowdown), respectively. No patient was class 1 at 6 and 12 months, suggesting a lack of drug response. In nonanaplastic meningiomas, Lutathera®'s antitumoral activity appeared delayed and more likely observed at six months, while no major response was observed under treatment. Moreover, its antitumoral activity persisted for 12-18 months following treatment initiation.

Contribution of the Photonic Component to the Ionization of the Atmosphere by Earth Crust Nuclides and Radioactive Emanations

Abstract—We investigate the contribution of gamma radiation of natural radionuclides constituting the Earth crust, radioactive emanations, and their decay product in the ground to the intensity of production of ion pairs in the atmosphere against the background of ionization of the atmosphere by radioactive gases flowing to the atmosphere from the ground and propagating together with their short-lived daughter products. The density of the radon flux to the atmosphere is estimated by three methods: the reservoir method, the integration of altitude profiles of volume activity of radon, based on gamma spectroscopic observation and diffusion model. The distribution of the gamma dose rate dose from the earth radionuclides in the soil and in the atmosphere is calculated using Gleant4 software. The propagation of the radon isotopes and their decay products in the atmosphere is calculated using large eddy simulations supplemented with kinematic simulations of the subgrid transport of a passive scalar. It is shown that depending on the specific activity of nuclides in the ground and the turbulent regime of the atmosphere, the total contribution of the γ-radiation to the ion pair production rate in the atmospheric boundary layer is approximately from 1% to 20% and increases upon a decrease in the penetrability of the upper ground layer for radioactive emanations.

Radiation Doses of Pine Stands in the Belarusian Sector of the 30-Kilometer Zone Around the Chernobyl Nuclear Power Plant at the Present Stage

The article presents the results of assessing the dose of external and internal irradiation of the tree tier of pine stands growing on the northern trace of the Belarusian sector of the 30-kilometer zone around the Chernobyl nuclear power plant at the present stage. It was found that in the most polluted experimental sites, the total dose of external and internal irradiation of the stand can reach 160 mGy/year. It is shown that internal irradiation is formed by beta radiation of radionuclides accumulated by aboveground phytomass, its contribution to the total dose can be 80%. The external irradiation of the stand is determined by the gamma radiation of 137Cs located in the soil. The results obtained are important for understanding the processes of formation of radiation-induced effects and assessing the effects of irradiation of living organisms.

Радиационная и пожарная опасность натриевого теплоносителя

Introduction. Nuclear power plants in the Russian Federation produce about 20 % of the total electricity. On the basis of fast neutron reactors using sodium as a coolant, Rosatom State Corporation is implementing the “Breakthrough” project aimed at the implementation of a nuclear fuel cycle using the energy potential of natural uranium. Study and generalization of information about fire and radiation hazards of sodium coolant is an urgent task to ensure safety in the operation of this type of reactors. Goals and objectives. The purpose of the article is an analytical study of information about sodium coolant radiation and fire hazard, published in domestic and foreign scientific literature. To achieve it, an analysis of fast neutron reactors operating in the world was carried out, the coolants used in fast reactors were considered. System analysis of radionuclides present in sodium coolant has been carried out, comparative diagrams according to radionuclide radiation properties are presented, the most dangerous radionuclides for humans present in the sodium coolant have been identified. The fire hazard of sodium metal and peculiarities of extinguishing fires associated with the leakage of sodium coolant in the primary and secondary circuits of the reactor plant are analyzed. Results and its discussion. At the present time, there is 1 experimental-industrial fast neutron reactor in operation in the world, located in Russia, and 1 experimental reactor in India and China. Sodium is used as a coolant in these reactors. As a result of the literature analysis from open sources, it was found that the main sources of impurities in the metal coolant are protective gas, structural and technological materials of the installation, and products of nuclear reactions. A systematic analysis of the properties of radionuclides present in the metal coolant made it possible to determine the most dangerous of them for human life and health. The fire hazard of sodium coolant is mainly due to its chemical activity. The main ways of extinguishing spilled sodium is isolation from oxygen by covering the puddle of metallic sodium with powdered fire-extinguishing MHS, powdered aluminum oxide or reduction of oxygen concentration in the air below 4 % by volume gas extinguishing with nitrogen, carbon dioxide or inert gases. Conclusions. As a result of the analysis of radionuclides present in the sodium coolant of a fast neutron reactor, it was found that the most dangerous for people are 24Na, 137Cs, 125Sb, 22Na, 239Pu, 54Mn, 110mAg, 131I. Based on the results of the analysis of the fire hazard of radioactive sodium, the most common fire extinguishing agents are established and the features of extinguishing fires that occur when a sodium coolant ignites are described.

ДОЗИМЕТРИЯ ТРИТИЯ НА КЛЕТОЧНОМ УРОВНЕ

Introduction 1. Tritium radioisotope and its energy spectrum 2. Methods for calculating doses from radiation of radionuclides 2.1 General equation for absorbed dose rate 2.2 Absorbed dose rate versus average energy 2.3 Formulas for calculating dose and S-values ​​from radiation of radionuclides 2.4 Method of dose point nuclei 2.5 MIRD effective stopping power method 2.6 Geometric factor 3. Analysis of S-value calculations by various methods 3.1 Values ​​of the CSDA range at low initial electron energies 3.2 Comparison of S-value calculations for low energy electrons 3.3 Comparison of tritium S-value calculations 4. Evaluation of S-value calculations in the absence of spherical symmetry Conclusion

Advanced diagnostic imaging of sentinel lymph node in early stage breast cancer.

Sentinel lymph node biopsy has been regarded as the standard procedure for early staging breast cancer. One of the key steps is to locate the sentinel lymph node (SLN). The recommended method is the joint use of blue dye and radioisotope. However, due to radionuclide radiation and high cost, it is urgent to develop more convenient and sensitive imaging methods to accurately locate SLN. This article discusses the advancement of accurately locating SLN by isotope tracer imaging, magnetic tracer method, computed tomographic lymphography, and trans‐lymphatic contrast‐enhanced ultrasound, as well as proposing new propose for clinical diagnosis.

Distribution of some natural and anthropogenic radionuclides in the sediments and seawater along the coastal areas of North Sulawesi

Studies on the radionuclide distribution of some naturally occurring radioactive materials (NORM) and anthropogenic radionuclides in the sediments of the coastal areas of North Sulawesi were conducted to provide baseline data for the effective monitoring of radioactive fallout in these areas. Sediment samples were collected by a van Veen grab samples about 100 – 300 m from the shoreline, and 60 L of seawater was pre-concentration to precipitated 137Cs. Activity concentration of the three main natural radionuclides (222Ra, 232Th, and 40K) and 137Cs were determined using a high-resolution HPGe gamma-spectroscopy system and presenting background about the radiological levels and assessing the associated hazards. The activity of 226Ra ranged from 2.1 to 9.5 Bq kg−1 with an average value of 5.9 Bq kg−1. The activity of 232Th varies from 2.4 to 10.4 Bq kg−1 with an average value of 5.2 Bq kg−1. The 40K ranges between 169.1 to 492.7 Bq kg−1 with an average value of 238.8 Bq kg−1. The average activity concentration of 40K (238.8 Bq kg−1) in the sediment samples was lower than the worldwide average concentration (420 Bq kg−1). The current level of activity 137Cs varied from 0.05 to 0.40 Bq kg−1 in sediment samples and 0.98 to 1.33 Bq m−3 in seawater samples. 134Cs in all samples were not detected or below the detection limit. This fact indicated that radioactive cesium in Celebes Sea areas of North Sulawesi still originated from global fallout and insignificant influenced by the FDNPP accident. All radionuclide radiation values in the recent study are lower than the world average. Therefore, the potential danger of radiation generated from the surrounding environment has not yet caused a radiological health impact for the people living on the coast of North Sulawesi. Natural and artificial radionuclide activity data in this study will be used as the basis for sedimentary activity along the coast of North Sulawesi.

Multiplex and In Vivo Optical Imaging of Discrete Luminescent Lanthanide Complexes Enabled by In Situ Cherenkov Radiation Mediated Energy Transfer.

Recently, we pioneered the application of Cherenkov radiation (CR) of radionuclides for the in situ excitation of discrete Eu(III) and Tb(III) complexes. CR is produced by isotopes decaying under emission of charged particles in dielectric media and exhibits a maximum intensity below 400 nm. We have demonstrated that luminescent lanthanide antenna complexes are ideal acceptors for Cherenkov radiation-mediated energy transfer (CRET). Here, we develop and assess peptide-functionalized Tb(III) and Eu(III) complexes in conjunction with CRET excitation by the positron emissive radioisotope 18F for simultaneous, multiplexed imaging and in vivo optical imaging. This work demonstrates, for the first time, that the detection of the luminescence emission of a discrete Eu(III) complex in vivo is feasible. Our results open possibilities for discrete luminescent lanthanide complexes to be used as diagnostic, optical tools for the intrasurgical guidance of tumor resection.

Some aspects of radiation protection in radionuclide therapy departments

The paper presents the data that allow calculate the attenuation factors in lead, tungsten and concrete of various thicknesses or the thickness of shielding made of these materials for a given attenuation factor for the spectra of gamma radiation of 131I and 177Lu radionuclides. Using these data the effectiveness of the protection of supporting equipment (portable containers, shielded syringes, etc.) and the possible doses of external radiation of medical personnel in the radionuclide therapy department were calculated. It is shown that there are short-term operations in the production process when a radiation source (container with a capsule with activity, syringe with activity), being near the body of a medical worker, creates a significant dose rate. For this reason the annual individual dose of external exposure of a medical worker can approach or exceed 1/3 of the dose limit. Calculation of the attenuation of 131I gamma radiation by stationary shield showed that the thickness of walls and floors made of concrete 200 – 400 mm will ensure that the permissible values of the dose rates of gamma radiation in the air do not exceed at annual turnover of activity in the radionuclide therapy department of ~ 3.3 · 1012 Bq.

Biodistribution of 131I in mice is influenced by circadian variations

Effects of radiation and biodistribution of radionuclides are often studied in animal models. Circadian rhythm affects many biological functions and may influence the biokinetics of radionuclides and observed responses. The aim of this study was to investigate if the time during the day of 131I injection affects the biodistribution and absorbed dose to tissues in mice. Biodistribution studies were conducted on male C57BL/6 N mice for three diurnal time-series: the animals were i.v. injected with 160 kBq 131I at 8 am, 12 pm or 4 pm. The activity concentration in organs and tissues was measured at 1 h to 7 days after administration and absorbed dose at day 7 was determined. Comparison between the three time-series showed statistically significant differences in activity concentration in all investigated tissues and organs. Administration performed at 12 pm resulted in general in higher absorbed dose to the organs than injection performed at 8 am and 4 pm. Time of day of administration affects the biodistribution of 131I in mice and consequently the absorbed dose to individual organs. These findings advocate that subsequent biodistribution studies and dosimetry calculations should consider time-point of administration as a variable that could influence the results.

Natural Radionuclides Determination and Radiological Hazard Assessments in Soil from Tual and Kei Islands, Indonesia

Natural radionuclides 226 Ra, 232 Th and 40 K in soil are the primary component of the background exposure sources of the population. Study of the external exposure due to gamma-ray radiation of natural radionuclides is important because this may contribute significantly to the total annual individual dose. The purpose of this study is to investigate the natural radionuclides in soils collected from Tual and Kei islands and assess the radiological hazard due to natural radionuclides contents in soil. The soil samples were analyzed for natural radionuclides 226 Ra, 232 Th and 40 K using gamma ray spectrometry. Radiological hazard parameters were estimated from the activity concentration of these radionuclides in order to assess health implication of exposure of the general public. The activity concentrations of 226 Ra, 232 Th and 40 K in soil samples varied from 7.50 Bq kg -1 to 6326 Bq kg -1 , 0.99 Bq kg -1 to 157 Bq kg -1 , 2.97 kg -1 to 98.91 Bq kg -1 with the average value of 2162 Bq kg -1 ; 69.68 Bq kg -1 and 30.74 Bq kg -1 , respectively. The absorbed dose rates due to the presence of 226 Ra, 232 Th and 40 K, in soil samples in the studied area vary between the range of 4.88 nGy h -1 and 3018.80 nGy h -1 with the average value of 1042 nGy h -1 . The corresponding outdoor annual effective doses ranged between 0.01 mSv y -1 and 3.70 mSv y -1 with the average value of 1.28 mSv y -1 . Radium equivalent activities are calculated to be in the range of 10.42 Bq kg -1 - 6553.03 Bq kg -1 with the average value of 2264 Bq kg -1 . The external and internal hazard indexes vary from 0.03 to 17.71 with the average value of 6.12 and 0.05 to 34.81 with the average value of 11.96, respectively. All calculated average radiological hazard indices were higher than the limits recommended for individual members of the public.

Гамма-активационный анализ селена на ускорителе электронов “Микротрон-сТ”

In this work, an activation analysis of selenium under its irradiation with bremsstrahlung gamma radiation on a cyclic electron accelerator “Microtron-sT” with an energy of 21 MeV is carried out irradiation was performed at room temperature for 1 h, the gamma-ray intensity was ~ 5·1013 γ/s. Irradiation was carried out on two types of state of the samples (Se) in the form of granules of the (osch), weight 5-10 mg, and microparticles (powder) obtained by mechanical dispersion. Samples in the state of microparticles were suspended in distilled water, in separate polyethylene capsule. On each sample, after irradiation with bremsstrahlung gamma radiation, the spectra of quantum radiation of radionuclides were measured. The measurements were carried out repeatedly in order to observe a decrease in the activity of the samples and their energy gamma spectrum. From the results obtained, it can be seen that all radionuclides are formed on selenium nuclei with different mass numbers by reactions: (γ, n), (γ, p), (γ, 2n), (γ, p + n). The half-life of (T1/2) in identified radionuclides is within 3.9 minutes — 119.8 days. The energy of emitted quanta by radionuclides is equal to from 121.1 to 657 keV. The radiation intensity of radionuclide gamma rays is in the range: 0.25-99.0%.

Markov chain Monte Carlo sampling for accurate estimation of spatial distribution of naturally occurring radionuclides radiation (232Th, 40K, and 238U) in Senegal

ABSTRACT An inaccurate quantification of the reference level of background radiation introduces an inherent statistical bias. Thus, it is necessary to develop a flexible and easy method for accurate characterization of naturally occurring radionuclides (NOR) reference background level in the mining area. In this paper, we propose the use of Bayesian modeling as an alternative statistics technique to study the spatial distribution of NOR. The Markov chain Monte Carlo (MCMC) approach is used to infer the statistical parameter of naturally occurring gamma-induced radionuclides such as 232Th, 40K and 228Ra. We used a bootstrapping method to obtain an accurate sub-sample and then exclude all potential outliers which are out of the Highest Density Interval (HDI). With the resampled sample, we build a model with a Bayesian statistics method with MCMC to draw an inference of the posterior distribution of the gamma-induced radionuclides.

Methods of calculation of radiation protection for operational safety optimization at working with radionuclide photon radiation sources

Methods of calculation of radiation protection for operational safety optimization at working with radionuclide photon radiation sources

Receptor radionuclide targeting for neuroendocrine tumors (NET) diagnostic and therapy

Neuroendocrine tumors (NET) represent a heterogeneous group of tumors originating from cells of neuroendocrine origin, which express somatostatin receptors (SSTR). This property allowed the successful development of radionuclides for diagnostic and peptide radionuclide radiation therapy (PRRT). This is the paradigm for the theragnostic concept in NET personalized medicine. The only phase III study to date (NETTER-1) clearly demonstrated the ability of 177Lutetium-based PRRT to improve progression-free survival in advanced intestinal NETs. In clinical practice, the indications are limited to G1-G2 well-differentiated NETs with high expression of SSTR. NETs with a low tumor burden and slow progression are probably the optimal indication. This treatment is now available in France. However, its precise position in the treatment algorithm remains to be explored. We provide an overview of receptor radionuclide utilization and mechanism in diagnostic and pretherapeutic imaging and we focus on PRRT for endocrine tumors.

Design-experimental assessment of radiological hazards in residential and industrial premises

Construction of residential and industrial buildings is associated with a wide application of both traditional and new structural and finishing materials. Radiological conditions in buildings are determined radiation of natural radionuclides contained in structural and finishing materials of buildings. Mostly around the world national criteria are used governing the content of natural radionuclides in building materials, based on the recommendations of international regulatory bodies. In Russia in order to justify admissibility of structural and finishing building materials in housing construction people use experimental methods. In European Union countries government suggests calculating estimation for assessment of the applicability different materials in various areas of housing and civil construction. Earlier, the authors established the fact of possible inconsistencies between Russian and European standards in different classes of materials. In order to compare the applicability of different approaches were held complex researches including experimental determination content of natural radionuclides in materials, calculation of dose rate in specific rooms and direct measurements of dose rates. As basic model authors used approach applied in the European Union countries. Experimental studies were performed using methods scintillation spectrometry and radiometry. The objects of research were premises with bearing and enclosing concrete structures faced with tiles. Experimental dose rate values were determined after deduction of the radiation background on the terrain. The conducted studies showed that the application of the computational model with the use of experimental values of the activity of natural radionuclides leads in some cases to incorrect values of dose rate in the premises, which is associated with the accepted value of the radiation background. Despite the simplicity of the proposed approach and its direct use can lead to unreliable results. So the coincidence of the calculated and experimental data is irregular. Obtained results allow to make the main conclusion about the limited application of the estimated approach to evaluation of radiological hazard in living quarters. The most reliable are the experimental approach, despite its great labor intensity. Calculate approach should be applied at the preliminary stage of rejection of materials.

Организация индивидуальной защиты персонала при проведении диагностических и лечебных процедур c использованием радионуклидных и генерирующих источников ионизирующего излучения

Purpose: To improve radiation safety of medical staff and patients during diagnostic and treatment procedures with using of radionuclide radiation sources.
 Materials and methods: Staff working conditions have been analyzed and the potential for using of various personal protective equipment has been assessed based on the developed framework of personal protection of medical staff and patients at nuclear medicine centers. In accordance with methods described in the current Russian standards, specimens of personal protective equipment manufactured at Russian industrial plants and suitable for use by medical staff and patients at nuclear medicine centers have been tested.
 Results: Results of laboratory tests of new advanced high-performance personal protective equipment of various purposes for protection of medical staff and patients during diagnostic and treatment procedures with using of radionuclide radiation sources are provided. Training and information documents and guidelines have been developed, including “Study guide on personal protection during diagnostic and treatment procedures with using of radionuclides and ionizing radiation sources” for various departments of the Institute of Continuing
 Vocational Education, State Research Center – Burnasyan Federal Medical Biophysical Center of the FMBA of Russia, and “Guidelines on personal protection of medical staff and patients during diagnostic and treatment procedures with using of radionuclides and ionizing radiation sources”.
 Conclusion: Study guide and Guidelines on personal protection of medical staff and patients at nuclear medicine centers during diagnostic and treatment procedures with using of radionuclide radiation sources, as well as the draft of the Standard guidelines on delivery of free personal protective equipment to medical staff have been developed based on the results of work and studies.

APPLICATION OF SURFACE COMPLEXATION AND ION EXCHANGE MODELLING FOR THE ESTIMATION OF BENTONITE SORPTION CAPACITY ON SELECTED RADIONUCLIDES UNDER POSSIBLE GEOLOGICAL DISPOSAL CONDITIONS IN LITHUANIA

Designing a repository for radioactive waste as a multi-barrier system with predefined multiple safety functions provides for the protection of people and environment from the harmful effect of the ionising radiation of radionuclides once released from high-level radioactive waste. The multi-barrier system is comprised of the engineered barrier system (EBS) and its surrounding natural environment. Because of the high retention capacity for the radionuclides, various forms of bentonite are usually considered as a part of the EBS in the design of radioactive waste repositories. Laboratory batch experiments with natural sediments illustrate that the sorption (and Kd values) is sensitive to aqueous chemical conditions, including the pH and the dissolved carbonate concentration as well as the mineralogy and surface area of the bentonite buffer. The cations considered for the study were chosen as covering a representative range of cations behaviour: from a weakly sorbed cation Cs(I) to moderately sorbed cation the Ni(II) and strongly sorbed cation, Eu(III). In this study, a potential retardation of sorbing radionuclides (Cs, Ni, Eu) as a function of aqueous chemical conditions in the groundwater of the Lithuanian crystalline basement contacting the bentonite material was estimated for the first time. The ion exchange and surface complexation models (SPNE/CE) and the computer program PHREEQC (USA) were applied for modelling the interaction within the radionuclide/water/bentonite system. The modelling of the Kd values under different pH conditions and a given partial pressure of carbon dioxide in the gas phase were performed. The highest value of Kd in the pCO2 open system and the strongest sorption dependence on pCO2 was estimated for Eu(I) among radionuclides being studied. There was estimated only a slight change in Kd values with respect to the temperature.DOI: http://dx.doi.org/10.5755/j01.ct.68.1.18875

Radionuclides in radiation-induced bystander effect; may it share in radionuclide therapy?

For many years in radiobiology and radiotherapy predominated the conviction that cellular DNA is the main target for ionizing radiation, however, the view has changed in the past 20 years. Nowadays, it is assumed that not only directed (targeted) radiation effect, but also an indirect (non-targeted) effect may contribute to the result of radiation treatment. Non-targeted effect is relatively well recognized after external beam irradiation in vitro and in vivo, and comprises such phenomena like radiation-induced bystander effect (RIBE), genomic instability, adaptive response and abscopal (out of field) effect. These stress-induced and molecular signaling mediated phenomena appear in non-targeted cells as variety responses resembling that observed in directly hit cells. Bystander effects can be both detrimental and beneficial in dependence on dose, dose-rate, cell type, genetic status and experimental condition. Less is known about radionuclide-induced non-targeted effects in radionuclide therapy, although, based on characteristics of the radionuclide radiation, on experiments in vitro utilizing classical and 3-D cell cultures, and preclinical study on animals it seems obvious that exposure to radionuclide is accompanied by various bystander effects, mostly damaging, less often protective. This review summarizes existing data on radionuclide induced bystander effects comprising radionuclides emitting beta- and alpha-particles and Auger electrons used in tumor radiotherapy and diagnostics. So far, separation of the direct effect of radionuclide decay from crossfire and bystander effects in clinical targeted radionuclide therapy is impossible because of the lack of methods to assess whether, and to what extent bystander effect is involved in human organism. Considerations on this topic are also included.

Radionuclide Disperse To Environtment From Pwr Reactor On Severe Accident Condition Using Maccs Program

<p>The atmosphere is an important pathway in the transfer of radionuclides from nuclear power plants into the environment and population. Acceptance of radiation dose to the environment and population affected by the radionuclides release and site conditions surrounding of the nuclear power plant. The radionuclides release in the atmosphere is determined by the dispersion coefficient parameter. The aim of this paper is to obtain dispersion coefficient and radionuclide released in Sebagin (West Bangka district) caused by severe accident condition from the PWR Nuclear Power Plant. Dispersion analysis of radionuclides into the environment from nuclear power PWR on severe accident conditions have been done using MACCS program. Reference for the calculation of source term fraction is selected from calculation results of the MELCOR computer code and it is implemented to PWR reactors Westinghouse 3411 MWth subject. The calculation of radionuclides release performed using MACCS program for aspiring nuclear power plant site in West Bangka. Simulation calculations for the area radius from 0.80 kmup to 20 km from the nuclear power plant site are performed. Meteorological datas used in calculation are the meteorology data from Sebagin meteorological stations for the years of 2012 period. The result is the dispersion coefficient decreases as a function of time and distance. The concentration of radionuclides through soil pathway decreases as a function of the distance, and the dominant contributor of radionuclide radiation Xe-133 and I-131. Radionuclide concentrations obtained through the air pathway decreases as a function of distance, and dominant contributors of radionuclide radiation is contributed also from I-131 and Xe-133. The presence of I-131 radionuclides are giving dangerous to humans, it is necessary to further treatment for prevent its impacts. </p>