ASSUMED-MODE MODELING FOR FAST-REACTOR CORE SEISMIC ANALYSIS

被引：0
|
作者：
MORAN, TJ [1 ]
机构：
[1] ARGONNE NATL LAB,ARGONNE,IL 60439
来源：
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY | 1978年 / 30卷 / NOV期
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：213 / 214
页数：2
相关论文
共 50 条
  • [1] METHODS FOR THE SEISMIC VERIFICATION OF A FAST-REACTOR CORE
    MARTELLI, A
    FORNI, M
    MURATORI, PG
    BONACINA, G
    NUCLEAR ENGINEERING AND DESIGN, 1985, 90 (03) : 317 - 330
  • [2] A METHOD TO ASSESS THE SEISMIC RESPONSE OF A FAST-REACTOR CORE WITH BARREL RESTRAINT
    DUTHIE, JC
    NUCLEAR ENGINEERING AND DESIGN, 1989, 114 (01) : 53 - 60
  • [3] FUEL MODELING IN FAST-REACTOR WHOLE CORE ACCIDENT CALCULATIONS
    WIDER, HU
    NUCLEAR ENGINEERING AND DESIGN, 1987, 101 (03) : 363 - 377
  • [4] RESEARCH AND DEVELOPMENT STUDIES ON PLANT AND CORE SEISMIC BEHAVIOR FOR A FAST-REACTOR
    MARTELLI, A
    FORNI, M
    MASONI, P
    MARESCA, G
    CASTOLDI, A
    MUZZI, F
    NUCLEAR ENGINEERING AND DESIGN, 1988, 106 (01) : 103 - 126
  • [5] Modal analysis of assumed-mode models of a flexible slewing beam
    Saad, Mohamad
    Piedboeuf, Jean-Claude
    Akhrif, Ouassima
    Saydy, Lahcen
    INTERNATIONAL JOURNAL OF MODELLING IDENTIFICATION AND CONTROL, 2006, 1 (04) : 325 - 337
  • [6] PROBLEMS IN MATHEMATICAL-MODELING OF FAST-REACTOR CORE RESTRAINT SYSTEMS
    MORAN, TJ
    MCLENNAN, GA
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1975, 22 (NOV16): : 560 - 560
  • [7] ADVANCES IN THE ANALYSIS OF FAST-REACTOR CORE AND COOLANT CIRCUIT STRUCTURES
    CHANG, YW
    EGGEN, DT
    IMAZU, A
    LIVOLANT, M
    NUCLEAR ENGINEERING AND DESIGN, 1992, 134 (01) : 37 - 58
  • [8] SCRAM AND NONLINEAR REACTOR SYSTEM SEISMIC ANALYSIS FOR A LIQUID-METAL FAST-REACTOR
    MORRONE, A
    NAHAVANDI, AN
    BRUSSALIS, WG
    NUCLEAR ENGINEERING AND DESIGN, 1976, 38 (03) : 555 - 566
  • [9] STUDY OF COMPACT FAST-REACTOR CORE DESIGNS
    HAMID, T
    OTT, KO
    NUCLEAR SCIENCE AND ENGINEERING, 1993, 113 (02) : 109 - 121
  • [10] Transient Thermohydraulic Processes in a Fast-Reactor Core
    Bogoslovskaya, G. P.
    Matyukhin, N. M.
    Mikhin, V. I.
    Sorokin, A. P.
    Atomic Energy, 80 (01):
12345