FUEL CLADDING THERMAL CONDUCTANCE FOR SPHERE-PAC MIXED CARBIDE FUEL

被引：0
|
作者：
PEDDICORD, KL
DEISS, E
BUTLER, T
机构：
[1] UNIV CALIF LOS ALAMOS NATL LAB, LOS ALAMOS, NM 87545 USA
[2] TEXAS A&M UNIV, COLLEGE STN, TX 77843 USA
[3] FED INST REACTOR RES, CH-5303 WURENLINGEN, SWITZERLAND
来源：
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY | 1984年 / 47卷
关键词：
D O I：
暂无
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：
引用
收藏
页码：195 / 196
页数：2
相关论文
共 50 条
  • [41] THERMAL INTERACTION OF MOLTEN CARBIDE FUEL WITH STAINLESS-STEEL CLADDING
    SULLIVAN, JE
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1975, 21 (JUN): : 305 - 306
  • [42] The MARINE experiment: Irradiation of sphere-pac fuel and pellets of UO2-x for americium breading blanket concept
    D'Agata, E.
    Hania, P. R.
    Freis, D.
    Somers, J.
    Bejaoui, S.
    Charpin, F. F.
    Baas, P. J.
    Okel, R. A. F.
    van Til, S.
    Lapetite, J. -M.
    Delage, F.
    NUCLEAR ENGINEERING AND DESIGN, 2017, 311 : 131 - 141
  • [43] FUEL - CLADDING CAP CONDUCTANCE - APPLICATION OF GAPCON-THERMAL-2 PROGRAM
    TINKA, I
    JADERNA ENERGIE, 1982, 28 (01): : 27 - 31
  • [44] Studying silicon carbide for nuclear fuel cladding
    Bragg-Sitton, Shannon
    Barrett, Kristine
    van Rooyen, Isabella
    Hurley, David
    Khafizov, Marat
    NUCLEAR ENGINEERING INTERNATIONAL, 2013, 58 (706): : 37 - 40
  • [45] SOL-GEL SPHERE-PAC (U,PU)O2 FUEL PERFORMANCE IN EBR-II IRRADIATION TESTS
    OLSEN, AR
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1971, 14 (02): : 596 - &
  • [46] COMPARISON OF SPHERE-PAC AND PELLET (U,PU)O2 FUEL PINS IN LOW-BURNUP INSTRUMENTED IRRADIATION TESTS
    FITTS, RB
    MILLER, FL
    NUCLEAR TECHNOLOGY, 1974, 21 (01) : 26 - 38
  • [47] AC-3-irradiation test of sphere-pac and pellet (U,Pu)C fuel in the US Fast Flux Test Facility
    Bart, G.
    Botta, F. B.
    Hoth, C. W.
    Ledergerber, G.
    Mason, R. E.
    Stratton, R. W.
    JOURNAL OF NUCLEAR MATERIALS, 2008, 376 (01) : 47 - 59
  • [48] FUEL-CLADDING GAP-CONDUCTANCE MODEL FOR LMFBR FUEL-ELEMENTS
    CHOW, LSH
    BILLONE, MC
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1976, 23 (JUN18): : 170 - 171
  • [49] FUEL MANAGEMENT OF PWR CORES WITH SILICON CARBIDE CLADDING
    Dobisesky, Jacob
    Richard, Joshua
    Pilat, Edward E.
    Kazimi, Mujid S.
    Carpenter, David M.
    NUCLEAR TECHNOLOGY, 2014, 186 (03) : 353 - 377
  • [50] MODELING OF FUEL CLADDING POSTIRRADIATION GAP IN MIXED-OXIDE FUEL PINS
    DUTT, DS
    BAKER, RB
    CHASTAIN, SA
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1973, 17 (NOV): : 175 - 175
12345