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From the comparison of obtained results with references, the suitable and precise simulating of transient schemes can be comprehended using the time-dependent second order average current nodal expansion method. For indicating the precision of the method, the numerical results of high (second) order approach also have been compared with the basic methodology i.e.
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In order to evaluate the implemented methodology, two popular transient problems are used including TWIGL two-dimensional seed-blanket reactor and three-dimensional LMW LWR. In this case, an adopted iterative approach is used for resolving the time-dependent three-dimensional multi-group neutron balance equations coupled with six-group precursor equations. Generally, nodal methods can accurately simulate the reactor core with coarse meshes as long as the sizes of a fuel assembly.
K AND N ENGINEERING SIMULATOR
In the present work, a time-dependent neutron diffusion simulator is developed utilizing the second order of average current nodal expansion method. In addition, the carried out calculations showed natural circulation of air could powerfully remove the deposited heat of neutron and gamma rays. When the hall contains 25 casks (any contains 16 55%-burnup 10-years cooled spent fuel assembly), maximum gamma and neutron dose rates at the external surface of the hall are 3.45 nSv/h and 3.45 μSv/h, respectively. The carried out calculations showed 30 cm thickness would fulfil total gamma and neutron dose rate limitation after the external surface of the concrete wall. ORIGEN and MCNPX computational codes were used to model the storage hall contained 25 Tehran Research Reactor spent fuel casks. The concrete wall thickness was discussed to keep the dose rate limit of 10 μSv/h (neutron and gamma) at its external side when 25 casks are available inside the hall. The hall structure was considered as ordinary concrete with an internal dimension of 5×6×5 m3. The present study aims to show the neutronic behavior and neutron/gamma dose rates of a designed hall for storage of the casks as a current technical, economic, safe and flexible solution, adaptable to any long and short-term SNF storage strategy. The spent fuel assemblies-contained casks are stored in interim storage facilities. Metal casks are used for the management and disposal of spent fuel and all types of radioactive waste worldwide. The management of high radioactive spent nuclear fuel (SNF) from research and power reactors has become a key topic of discussion in the nuclear communities.
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** Based on the latest report from the Journals Commission Ranking of Ministry of Science, Research and Technology (MSRT) in 2021, RADIATION PHYSICS and ENGINEERING has been included in the list of scientific journals of MSRT and has been ranked as grade B.**Ĭontact management of high radioactive spent nuclear fuel (SNF) from research and power reactors has become a key topic of discussion in the nuclear communities. Papers dealing with nuclear radiation and radionuclide techniques, nuclear techniques and radiation processing, nuclear energy science and technology and nuclear physics in both experimental and theoretical field, applied in physics, chemistry, biophysics, biology, medicine, medical physics, engineering and environmental sciences are welcome. The purpose of the journal is to provide a high quality medium for the publication of substantial, original and scientific papers on the development and the enhancement of nuclear physics and nuclear engineering researches at the national as well as international level. Toosi University of Technology jointly with the Nuclear Society of Iran (NSI). Radiation Physics and Engineering (RPE) is an international scientific-research journal published quarterly by K.