DEVELOPING THE CODE FOR ANALYSIS OF HTGR FLUID DYNAMIC CONTROL CHARACTERISTICS.

被引:0
|
作者
Tanaka, Mitsuhiro
Izaki, Makoto
Koike, Hiroyuki
Tokumitsu, Masashi
机构
来源
FAPIG (First Atomic Power Industry Group) | 1983年 / 103期
关键词
D O I
暂无
中图分类号
学科分类号
摘要
NUCLEAR REACTORS, HIGH TEMPERATURE
引用
收藏
页码:7 / 15
相关论文
共 50 条
  • [1] INFLUENCE OF FIXING THE EDGES OF A CYLINDRICAL SHELL WITH CONVEYING FLUID ON ITS DYNAMIC CHARACTERISTICS.
    Horacek, J.
    Zolotarev, I.
    Soviet applied mechanics, 1984, 20 (08): : 756 - 765
  • [2] Analysis of the turbine deblading in an HTGR with the CATHARE code
    Saez, M
    Tauveron, N
    Chataing, T
    Geffraye, G
    Briottet, L
    Alborghetti, N
    NUCLEAR ENGINEERING AND DESIGN, 2006, 236 (5-6) : 574 - 586
  • [3] SIMULATION OF VEHICLE DYNAMIC BRAKING CHARACTERISTICS.
    Aurora, B.R.
    Journal of Automotive Engineering, 1972, 3 (08): : 13 - 19
  • [4] ANALYSIS OF MODFET MICROWAVE CHARACTERISTICS.
    Roblin, Patrick
    Kang, Sungchoon
    Ketterson, Andrew
    Morkoc, Hadis
    IEEE Transactions on Electron Devices, 1987, ED-34 (09) : 1919 - 1928
  • [5] ANALYSIS OF ROBOT WORK CHARACTERISTICS.
    NOF, SHIMON Y.
    FISHER, EDWARD L.
    Industrial Robot, 1982, V 9 (N 3): : 166 - 171
  • [6] DESIGNING INDUCTION MOTORS WITH PRESCRIBED DYNAMIC CHARACTERISTICS.
    Zagorskii, A.E.
    Galustyan, K.M.
    Soviet electrical engineering, 1978, 49 (09): : 80 - 84
  • [7] PISTON SYSTEM FOR EXAMINING FLOWMETER DYNAMIC CHARACTERISTICS.
    Ovodov, G.I.
    Raskovalkina, E.A.
    Seifer, A.L.
    1600, (28):
  • [8] Step Pneumohydraulic Drive and Its Dynamic Characteristics.
    Katkovnik, V.Ya.
    Filipov, I.B.
    Raitsin, M.V.
    Fam Van Khao
    Trudy LPI, 1982, (382): : 102 - 107
  • [9] SEWER NETWORK ROUTING BY DYNAMIC WAVE CHARACTERISTICS.
    Sevuk, A.Suha
    Yen, Ben Chie
    1982, 108 (HY3): : 379 - 398
  • [10] Improvement and verification of the DeCART code for HTGR core physics analysis
    Cho, Jin Young
    Han, Tae Young
    Park, Ho Jin
    Hong, Ser Gi
    Lee, Hyun Chul
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2019, 51 (01) : 13 - 30