<abstract xmlns="http://www.w3.org/1999/xhtml">The main objective of 235U irradiation is to obtain the 99mTc isotope, which is widely used in the domain of medical diagnostics. The decisive factor determining its availability, despite its short lifetime, is a reaction of radioactive decay of 99Mo into 99mTc. One of the possible sources of molybdenum can be achieved in course of the 235U fission reaction. The paper presents activities and the calculation results obtained upon the feasibility study on irradiation of 235U targets for production of 99Mo in the MARIA research reactor. Neutronic calculations and analyses were performed to estimate the fission products activity for uranium plates irradiated in the reactor. Results of dummy targets irradiation as well as irradiation uranium plates have been presented. The new technology obtaining 99Mo is based on irradiation of high-enriched uranium plates in standard reactor fuel channel and calculation of the current fission power generation. Measurements of temperatures and the coolant flow in the molybdenum installation carried out in reactor SAREMA system give online information about the current fission power generated in uranium targets. The corrective factors were taken into account as the heat generation from gamma radiation from neighbouring fuel elements as well as heat exchange between channels and the reactor pool. The factors were determined by calibration measurements conducted with aluminium mock-up of uranium plates. Calculations of fuel channel by means of REBUS code with fine mesh structure and libraries calculated by means of WIMS-ANL code were performed.</abstract>

Production of Fission Product 99Mo using High-Enriched Uranium Plates in Polish Nuclear Research Reactor MARIA: Technology and Neutronic Analysis

<abstract xmlns="http://www.w3.org/1999/xhtml">An industrial gauge for measuring thickness of a gold coating layer deposited on a steel base through detection of the backscattered beta particles has been described. 3H, 14C and 63Ni pure beta emitters have been tested as the radioisotopic sources of the system individually in a fixed geometry. Analytical calculations have been performed in each case. Furthermore, simulations based on Monte Carlo stochastic technique (MCNP) have been processed. The obtained results from both methods have been compared to define the sensitivity of the system in each case. Finally for the first time, fuzzy TOPSIS method has been used for choosing the best source in the defined geometry for manufacturing, considering the following three criteria: (a) saturation thickness, (b) precision and (c) sensitivity. Results have shown that 3H source is the best alternative to the introduced measuring system.</abstract>

Department of Radiation Application, Shahid Beheshti University G. C, Tehran, Iran, Tel: +98 912 439 2064

Department of Industrial Engineering, K. N. Toosi University of Technology, Tehran, Iran

Beta-backscattering Thickness-meter Design and Evaluation with Fuzzy TOPSIS Method

<abstract xmlns="http://www.w3.org/1999/xhtml">Verification of calculations of the depth-dose distributions in water, using GEANT4 (version of 4.9.3) and MCNPX (version of 2.7.0) Monte Carlo codes, was performed for the scatterer-phantom system used in the dosimetry measurements in the proton therapy of eye tumours. The simulated primary proton beam had the energy spectra distributed according to the Gauss distribution with the cut at energy greater than that related to the maximum of the spectrum. The energy spectra of the primary protons were chosen to get the possibly best agreement between the measured relative depth-dose distributions along the central-axis of the proton beam in a water phantom and that derived from the Monte Carlo calculations separately for the both tested codes. The local depth-dose differences between results from the calculations and the measurements were mostly less than 5% (the mean value of 2.1% and 3.6% for the MCNPX and GEANT4 calculations). In the case of the MCNPX calculations, the best fit to the experimental data was obtained for the spectrum with maximum at 60.8 MeV (more probable energy), FWHM of the spectrum of 0.4 MeV and the energy cut at 60.85 MeV whereas in the GEANT4 calculations more probable energy was 60.5 MeV, FWHM of 0.5 MeV, the energy cut at 60.7 MeV. Thus, one can say that the results obtained by means of the both considered Monte Carlo codes are similar but they are not the same. Therefore the agreement between the calculations and the measurements has to be verified before each application of the MCNPX and GEANT4 codes for the determination of the depth-dose curves for the therapeutic protons.</abstract>

Verification of the use of GEANT4 and MCNPX Monte Carlo Codes for Calculations of the Depth-Dose Distributions in Water for the Proton Therapy of Eye Tumours

<abstract xmlns="http://www.w3.org/1999/xhtml">One of the main issues in safety and control systems design of power and research reactors is to prevent accidents or reduce the imposed hazard. Control rod worth plays an important role in safety and control of reactors. In this paper, we developed a justifiable approach called D4D4 to estimate the control rod worth of a VVER-1000 reactor that enables to perform the best estimate analysis and reduce the conservatism that utilize DRAGON4 and DONJON4. The results are compared with WIMS-D4/CITATION to show the effectiveness and superiority of the developed package in predicting reactivity worth of the rod and also other reactor physics parameters of the VVER-1000 reactor. The results of this study are in good agreement with the plant's FSAR.</abstract>

Estimation of Control Rod Worth in a VVER-1000 Reactor using DRAGON4 and DONJON4

<abstract xmlns="http://www.w3.org/1999/xhtml">In this paper, an electromagnetic levitation system was used with a synchronous motor to navigate the control rod of a small-type research reactor. The result from this prototype magnetic levitation system was in agreement with simulation results. The control system was programmed in MATLAB through open-loop system, closed-loop with state feedback and closed-loop with state feedback integral tracking. The final control system showed the highest performance with a low positioning error. Our results showed that the developed control system has the potential to be used as a reliable actuator in nuclear reactors to satisfy higher performance and safety.</abstract>

Department of Electrical Engineering, Aliabad Katoul branch, Islamic Azad University, Aliabad Katoul, Iran, Tel: +98 911 353 2381

Department of Mechanical Engineering, Sirjan University of Technology, Kerman, Iran

A Novel Control-rod Drive Mechanism via Electromagnetic Levitation in MNSR

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Nukleonika publish articles from the fields of nuclear sciences especially of nuclear chemistry, radiation chemistry, radiation physics, chemistry of isotopes, radiobiology, and nuclear techniques in industry and environmental protection.  Why subscribe and read   Offers high quality scientific contribution from the following areas: radiochemistry, radiation measurements, application of radionuclides in various branches of science and technology, chemistry of f-block elements, radiation chemistry, radiation physics, activation analysis, nuclear medicine, radiobiology, radiation safety, nuclear industrial electronics, environmental protection, radioactive wastes, nuclear technologies in material and process engineering, radioisotope diagnostic methods of engineering objects, nuclear reactors and nuclear power, reactor physics, nuclear safety, fuel cycle, reactor calculations, nuclear chemical engineering, nuclear fusion, plasma physics;  available in print and electronic format;  double-blind peer reviewed;  one of the leading periodicals in fundamental, experimental, applied and theoretical aspects of nuclear sciences worldwide.   Why submit   Worldwide accessibility of articles;  Access of articles in abstracting databases;  Language correction service;  Hope in IF increase.   Archiving  Sciendo archives the contents of this journal in Portico - digital long-term preservation service of scholarly books, journals and collections.  Plagiarism Policy  The editorial board is participating in a growing community of Similarity Check System's users in order to ensure that the content published is original and trustworthy. Similarity Check is a medium that allows for comprehensive manuscripts screening, aimed to eliminate plagiarism and provide a high standard and quality peer-review process. 

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Volume 59 (2014): Issue 2 (June 2014)

Production of Fission Product ⁹⁹Mo using High-Enriched Uranium Plates in Polish Nuclear Research Reactor MARIA: Technology and Neutronic Analysis

Beta-backscattering Thickness-meter Design and Evaluation with Fuzzy TOPSIS Method

Verification of the use of GEANT4 and MCNPX Monte Carlo Codes for Calculations of the Depth-Dose Distributions in Water for the Proton Therapy of Eye Tumours

Estimation of Control Rod Worth in a VVER-1000 Reactor using DRAGON4 and DONJON4

A Novel Control-rod Drive Mechanism via Electromagnetic Levitation in MNSR

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