URANIUM STARTUP FAST REACTORS WITH METAL FUEL USING ONCE-THROUGH FUEL CYCLE

被引:1
|
作者
Fei, T. [1 ]
Driscoll, M. J. [1 ]
Shwageraus, E. [1 ]
机构
[1] MIT, Dept Nucl Sci & Engn, Cambridge, MA 02139 USA
关键词
uranium startup fast reactors; metal fuel;
D O I
10.13182/NT13-21
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 purpose of this study was to demonstrate the neutronic feasibility and competitive fuel cycle economics of sodium fast reactors operating with uranium metal (UZr) fuel on a once-through fuel cycle. Uranium startup fast reactors (USFRs) decouple their deployment from that of expensive reprocessing and recycle facilities. This could facilitate and speed up the deployment of conventional fast reactors, which, in their traditional designs, heavily depend on the availability of reprocessing facilities for transuranic fuel production. The uranium requirement and fuel cycle cost of studied USFR core designs are calculated to be comparable to those of typical light water reactors. The main design constraint is the fast neutron fluence imposed on the cladding material, which is required to be below 5.0 X 10(23) n/cm(2) even for advanced oxide dispersion strengthened steels. Therefore, moderators need to be inserted in the fuel assemblies to lower the fast neutron flux so that the fuel residence time limited by neutron fluence can be extended to match the reactivity limited fuel residence time. In this study, magnesium oxide is used for reflectors as well as for the moderator.
引用
收藏
页码:378 / 389
页数:12
相关论文
共 50 条
  • [41] THE BACK END OF THE NUCLEAR-FUEL CYCLE - TECHNICAL AND ECONOMIC-ANALYSIS .1. ONCE-THROUGH CYCLE
    ROGLANSRIBAS, J
    SPINRAD, BI
    NUCLEAR TECHNOLOGY, 1990, 89 (03) : 341 - 349
  • [42] Modeling, simulation, and control of multi-fuel once-through boilers
    DeJager, B
    Anneveld, H
    DeBlok, F
    CONTROL OF POWER PLANTS AND POWER SYSTEMS (SIPOWER'95), 1996, : 83 - 88
  • [43] Status of the Development and Production of Uranium–Plutonium Fuel for Fast Reactors
    F. G. Reshetnikov
    Atomic Energy, 2001, 91 : 998 - 1002
  • [44] URANIUM-PLUTONIUM MONONITRIDE FUEL MATERIALS FOR FAST REACTORS
    PARDUE, WM
    SMITH, RA
    ROUGH, FA
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1966, 9 (01): : 37 - &
  • [45] THE FUEL-CYCLE OF FAST-NEUTRON REACTORS
    BEKIARIAN, A
    ANNALES DES MINES, 1984, 191 (01): : 55 - 62
  • [46] Combined pyroprocessing fuel cycle for VVER and fast reactors
    Petrov, AV
    Usynin, GB
    Usynina, SG
    ATOMIC ENERGY, 1998, 85 (06) : 880 - 885
  • [47] ONCE-THROUGH THORIUM CYCLE FOR BWRS
    TOWNSEND, DB
    CROWTHER, RL
    WOLTERS, RA
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1979, 32 (JUN): : 354 - 355
  • [48] Applying US metal fuel experience to new fuel designs for fast reactors
    Crawford, Douglas C.
    Porter, Douglas L.
    PROGRESS IN NUCLEAR ENERGY, 2024, 171
  • [49] Fuel Cycle Studies on the Uranium Utilization Efficiency and Minor Actinide Burning in Gas Cooled Fast Reactors
    Halasz, M.
    Szieberth, M.
    Feher, S.
    Reiss, T.
    2013 4TH INTERNATIONAL YOUTH CONFERENCE ON ENERGY (IYCE), 2013,
  • [50] PEBBLE BED HTR WITH ONCE THROUGH FUEL CYCLE
    TEUCHERT, E
    RUTTEN, HJ
    HAAS, KA
    ATOMWIRTSCHAFT-ATOMTECHNIK, 1977, 22 (10): : 524 - 525