PRELIMINARY NEUTRONICS CALCULATIONS FOR CONVERSION OF THE TEHRAN RESEARCH REACTOR CORE FROM HEU TO LEU FUEL

被引:0
|
作者
NEJAT, SMR [1 ]
机构
[1] GILAN UNIV,FAC SCI,DEPT PHYS,RASHT,IRAN
关键词
RESEARCH REACTOR; NEUTRONICS CALCULATIONS; FUEL CONVERSION;
D O I
10.13182/NT93-A34842
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The 5-MW highly enriched uranium (HEU)-fueled Tehran Research Reactor is considered for conversion to high-density, low-enriched uranium (LEU) fueL A preliminary neutronics calculation is performed as part of the con version goal. In this study, two cores are considered: the HEU reference core and a proposed LEU core similar to the reference core, using standardized U3Si2 plates with the option of different U-235 loadings. Various possibilities are investigated for the con version of HEU to LEU fuel elements with 20% enriched U-235 loadings of 207 to 297 g U-235/element. For the same equilibrium cycle length, the fuels are compared for flux, power distribution, burnup, and reactivity.
引用
收藏
页码:187 / 198
页数:12
相关论文
共 50 条
  • [1] Transition Core Analysis for HEU to LEU Fuel Conversion at the University of Missouri Research Reactor
    Cowherd, Wilson
    Stillman, John
    Gahl, John
    Foyto, Leslie
    Wilson, Erik
    NUCLEAR TECHNOLOGY, 2021, 207 (02) : 167 - 181
  • [2] Neutronic evaluations for MNSR research reactor core conversion from HEU to LEU
    Abtin, F.
    Feghhi, S. A. H.
    Jafarikia, S.
    ANNALS OF NUCLEAR ENERGY, 2013, 51 : 69 - 73
  • [3] Reliability of neutronics characteristics prediction for reactor MARIA core conversion to LEU fuel
    Marcinkowska, Z. E.
    Kulikowska, T. A.
    ANNALS OF NUCLEAR ENERGY, 2013, 59 : 92 - 99
  • [4] ANALYSIS OF LOSS-OF-FLOW ACCIDENTS FOR THE NIST RESEARCH REACTOR WITH FUEL CONVERSION FROM HEU TO LEU
    Baek, J. S.
    Cuadra, A.
    Cheng, L. -Y.
    Hanson, A. L.
    Brown, N. R.
    Diamond, D. J.
    NUCLEAR TECHNOLOGY, 2015, 189 (01) : 71 - 86
  • [5] The HOR HEU LEU core conversion
    Gibcus, HPM
    De Vries, JW
    De Leege, PFA
    RRFM'99: 3RD INTERNATIONAL TOPICAL MEETING ON RESEARCH REACTOR FUEL MANAGEMENT, 1999, : 83 - 88
  • [6] THERMAL-HYDRAULIC ANALYSIS FOR HEU AND LEU TRANSITIONAL CORE CONVERSION OF THE MIT RESEARCH REACTOR
    Kim, Sung Joong
    Hu, Lin-Wen
    Dunn, Floyd
    NUCLEAR TECHNOLOGY, 2013, 182 (03) : 315 - 334
  • [7] Core conversion analyses of the Syrian MNSR reactor from HEU to LEU and MEU fuel with homogeneously mixed burnable poisons
    Ghazi, N.
    Hassan, H. Haj
    Hainoun, A.
    APPLIED RADIATION AND ISOTOPES, 2009, 67 (10) : 1919 - 1924
  • [8] Neutronic Analysis of the Oregon State TRIGA Reactor in Support of Conversion from HEU Fuel to LEU Fuel
    Hartman, M. R.
    Keller, S. T.
    Reese, S. R.
    Robinson, B.
    Stevens, J.
    Matos, J. E.
    Marcum, W. R.
    Palmer, T. S.
    Woods, B. G.
    NUCLEAR SCIENCE AND ENGINEERING, 2013, 174 (02) : 135 - 149
  • [9] Modeling and Analysis of Conversion HEU-LEU for IAEA Research Reactor
    Aziz, Moustafa
    Hassan, Mohga
    ARAB JOURNAL OF NUCLEAR SCIENCES AND APPLICATIONS, 2013, 46 (04): : 182 - 188
  • [10] Assessment of fuel conversion from HEU to LEU in the Syrian MNSR reactor using the MCNP code
    Khattab, K.
    Sulieman, I.
    PROGRESS IN NUCLEAR ENERGY, 2009, 51 (6-7) : 727 - 730