Autors: Kadalev, S. H.
Title: THERMAL HYDRAULIC CALCULATIONS OF THE IRT-SOFIA RESEARCH REACTOR WITH LEU FUEL IRT-4M
Keywords: thermal-hydraulic calculations, IRT-Sofia reactor, IRT-4M LE

Abstract: The neutronic calculations of the IRT–Sofia research reactor with fuel assemblies (FA) of the IRT–4M type, containing low enriched uranium (19.75%),confirmed the justness of the selection of its initial core configuration. On the basis of the neutronic calculation results the thermal-hydraulic calculations were done by PLTEMP code. Three possible operational regimes have been considered. For each of them the margin coefficients of the water onset of the nucleate boiling (ONB) have been determined. An analysis has been made on the fuel element surface for the particular fuel assembly with maximum power density. The calculations have been accomplished for the core water inlet temperature of 45 ◦C. The results are in compliance with the thermal-hydraulic safety requirements. This is valid for all analyzed regimes.

References

    Issue

    Compt. rend. Acad. bulg. Sci., vol. 65, issue 8, 2012, Bulgaria, BAS, ISBN 1310 – 1331

    Цитирания (Citation/s):
    1. Measurement of isothermal temperature reactivity coefficient at research reactor with IRT-4M fuel - 2014 - от чужди автори в чужди издания, неиндексирани в Scopus или Web of Science
    2. IRT-Sofia, HEU to LEU conversion: Regulatory approval tasks solution overview - 2014 - в издания, индексирани в Scopus или Web of Science
    3. Steady-State Safety Analysis of Ghana Research Reactor-1 With Low-Enriched-Uranium Core - 2020 - от чужди автори в чужди издания, неиндексирани в Scopus или Web of Science
    4. Thermal-Hydraulic Analysis of the LEU-Fueled Dalat Nuclear Research Reactor - 2021 - в издания, индексирани в Scopus или Web of Science

    Вид: статия в списание, публикация в издание с импакт фактор