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    Wyświetlanie 1-4 z 4
    Tytuł:
    Application of the generally available WIMS versions to modern PWRs
    Autorzy:
    Kulikowska, T.
    Stadnik, A.
    Andrzejewski, K.
    Boettcher, A.
    Powiązania:
    https://bibliotekanauki.pl/articles/147884.pdf
    Data publikacji:
    2012
    Wydawca:
    Instytut Chemii i Techniki Jądrowej
    Tematy:
    reactor calculations
    lattice spectrum code
    resonance integrals
    gadolinium bearing fuel
    Opis:
    The generally available versions of WIMS (Winfrith improved multigroup scheme) code have been used at the Institute of Atomic Energy POLATOM (IEA POLATOM, Otwock/Świerk, Poland) for a variety of reactor lattice analyses since 1974. With planned construction of new generation PWRs (power water reactors) in Poland, a question of WIMSD-5B version applicability to lattice calculations of strongly heterogeneous assemblies with gadolinium poisoned pins became actual. The present paper deals with modeling of the fuel assemblies using the version of WIMSD-5B extended at the IEA POLATOM. It was shown that with a careful choice of computational options the code properly describes main physical parameters of modern PWR fuel assemblies.
    Źródło:
    Nukleonika; 2012, 57, 1; 87-93
    0029-5922
    1508-5791
    Pojawia się w:
    Nukleonika
    Dostawca treści:
    Biblioteka Nauki
    Artykuł
    Tytuł:
    Production of fission product 99Mo using high-enriched uranium plates in Polish nuclear research reactor MARIA: Technology and neutronic analysis
    Autorzy:
    Jaroszewicz, J.
    Marcinkowska, Z.
    Pytel, K.
    Powiązania:
    https://bibliotekanauki.pl/articles/147625.pdf
    Data publikacji:
    2014
    Wydawca:
    Instytut Chemii i Techniki Jądrowej
    Tematy:
    fission products
    99Mo production
    neutronic calculations
    research reactor
    Opis:
    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.
    Źródło:
    Nukleonika; 2014, 59, 2; 43-52
    0029-5922
    1508-5791
    Pojawia się w:
    Nukleonika
    Dostawca treści:
    Biblioteka Nauki
    Artykuł
    Tytuł:
    Obliczenia neutronowe reaktora AP1000
    Neutronic calculations of the AP1000 reactor
    Autorzy:
    Suchcicki, Szymon
    Powiązania:
    https://bibliotekanauki.pl/articles/2055828.pdf
    Data publikacji:
    2021
    Wydawca:
    Instytut Chemii i Techniki Jądrowej
    Tematy:
    AP1000
    SCALE
    PARCS
    reaktor jądrowy
    obliczenia neutronowe
    nuclear reactor
    neutronic calculations
    Opis:
    W artykule przedstawiono opis obliczeń neutronowych przeprowadzonych w Państwowej Agencji Atomistyki dla reaktora AP1000. Zaprezentowano krótką charakterystykę tego reaktora, opisano zastosowane kody obliczeniowe oraz przedstawiono wyniki obliczeń i ich porównanie z wynikami zawartymi w amerykańskim raporcie „AP1000 Design Control Document”. Przedstawiono również plany dalszego wykorzystania stworzonych modeli obliczeniowych.
    The paper presents a description of neutronic calculations for the AP1000 reactor performed at the National Atomic Energy Agency of the Republic of Poland (PAA). A short characteristic of the reactor is presented, applied computer codes are described and results of the calculations and their comparison with results included in the "AP1000 Design Control Document" are presented. Plans for further use of the created computational models are also discussed.
    Źródło:
    Postępy Techniki Jądrowej; 2021, 4; 2--6
    0551-6846
    Pojawia się w:
    Postępy Techniki Jądrowej
    Dostawca treści:
    Biblioteka Nauki
    Artykuł
    Tytuł:
    Assessment of Radiological Dose around a 3-MW TRIGA Mark-II Research Reactor
    Autorzy:
    Rahman, A. F. M. M.
    Shamsuzzaman, M.
    Rahman, M. S.
    Uddin, K.
    Yeasmin, S.
    Nazmul, Haque H. M.
    Akramuzzaman, M. M.
    Chakraborty, S. R
    Powiązania:
    https://bibliotekanauki.pl/articles/412377.pdf
    Data publikacji:
    2013
    Wydawca:
    Przedsiębiorstwo Wydawnictw Naukowych Darwin / Scientific Publishing House DARWIN
    Tematy:
    source term
    release rate
    TRIGA Mark-II reactor
    dispersion
    ingestion and deposition of radionuclide
    Gaussian plume model
    dose calculations
    Opis:
    A hypothetical accidental case of a 3-MW TRIGA Mark-II research reactor has been assumed to assess the radiological consequences due to the deposition of 137Cs and 90Sr on ground, vegetation, milk and meat. The air concentrations in sixteen cardinal directions have been estimated where the maximum concentration has been found to be at 110 m distance from the core of the reactor for all the directions. Calculated maximum doses of 137Cs, 90Sr and both 137Cs and 90Sr have been found to be within the ranges of 0.005-0.014 μSv hr–1, 0.013-0.036 μSv hr–1 and 0.018-0.05 μSv hr–1, respectively for all the directions, which are below the measured background dose limit 0.25 μSv hr–1 and also within the IAEA acceptable dose rate limit of 0.5 μSv hr–1. The calculated low doses due to the aforementioned radionuclides can be considered negligible with regard to the radiation hazards. The relationship between total effective dose rate for various pathways (i.e. immersion, inhalation, ground deposition, and ingestion of contaminated vegetation, milk, meat) and air concentration in all the directions has been established. Obtained relation reveals that the total effective dose rate is directly proportional to the air concentration, and the overall proportionality constants for 137Cs and 90Sr radionuclides have been obtained as 0.57 and 0.28, respectively. This study might provide information on the radiological safety required for the radiation protection purposes of the people living in the vicinity of the reactor site.
    Źródło:
    International Letters of Chemistry, Physics and Astronomy; 2013, 10, 2; 183-200
    2299-3843
    Pojawia się w:
    International Letters of Chemistry, Physics and Astronomy
    Dostawca treści:
    Biblioteka Nauki
    Artykuł
      Wyświetlanie 1-4 z 4

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