Analysis of HCDA

Abstract Safety regulation requires that the containment of fast reactors be analyzed to a spectrum of hypothetical core-disruptive accidents (HCDAs). To demonstrate the reactor containment can sustain the consequences of HCDAs, studies must be made to understand the reactor core behavior under HCDA conditions, to establish the consequences of HCDAs, to provide features to mitigate the effects of HCDAs, and to determine the response of the reactor primary system to HCDA loads. This paper reviews some approaches and methods used in the experimental and numerical analyses.

[1]  D. J. Cagliostro,et al.  Experiments on the response of rigid and flexible reactor vessel models to a simulated hypothetical core disruptive accident. [LMFBR] , 1976 .

[2]  S. Giuliani,et al.  Lagrangian and Eulerian Finite Element Techniques for Transient Fluid-Structure Interaction Problems , 1977 .

[3]  J. L. Graveleau,et al.  Calculation of Fluid-Structure Interaction for Reactor Safety with the Cassiopee Code , 1979 .

[4]  L. P. Walker,et al.  RESPONSE OF ENRICO FERMI REACTOR TO TNT SIMULATED NUCLEAR ACCIDENTS , 1964 .

[5]  J. M. Kennedy,et al.  Theory and application of a quasi-Eulerian fluid element for the STRAW code. [LMFBR] , 1978 .

[6]  Y. W. Chang,et al.  Evaluation of Lagrangian, Eulerian, and arbitrary Lagrangian-Eulerian methods for fluid-structure interaction problems in HCDA analysis , 1979 .

[7]  R. F. Kulak.  Finite element formulation for fluid-structure interaction in three-dimensional space , 1979 .

[8]  W. T. Sha,et al.  VENUS: A TWO-DIMENSIONAL COUPLED NEUTRONICS-HYDRODYNAMICS COMPUTER PROGRAM FOR FAST-REACTOR POWER EXCURSIONS. , 1970 .

[9]  H. Y. Chu,et al.  ALICE: a hybrid Lagrangian-Eulerian code for calculating fluid-structure interaction transients in fast-reactor containment. [LMFBR] , 1979 .

[10]  J. Gvildys,et al.  TWO-DIMENSIONAL HYDRODYNAMICS ANALYSIS FOR PRIMARY CONTAINMENT. , 1969 .

[11]  W. E. Johnson,et al.  OIL, A CONTINUOUS TWO-DIMENSIONAL EULERIAN HYDRODYNAMIC CODE , 1965 .

[12]  W. Herrmann,et al.  Evaluation of computational techniques for LMFBR safety analyses , 1978 .

[13]  G. L. Goudreau,et al.  Coupled fluid-structure method for pressure suppression analysis , 1979 .

[14]  Y. W. Chang,et al.  Comparison of REXCO code predictions with flexible vessel experiments , 1978 .

[15]  H Y Chu.  ALICE: an arbitrary Lagrangian-Eulerian code for analyzing FBR containment response to HCDA , 1979 .

[16]  C. Y. Wang.  Comparison of ICECO code predictions with flexible vessel experiments , 1978 .

[17]  M. Wilkins.  Calculation of Elastic-Plastic Flow , 1963 .

[18]  J. E. Ash,et al.  COMPARISON OF A TWO-DIMENSIONAL HYDRODYNAMICS CODE (REXCO) TO EXCURSION EXPERIMENTS FOR FAST REACTOR CONTAINMENT. , 1972 .

[19]  A. H. Marchertas,et al.  Analysis and application of prestressed concrete reactor vessels for LMFBR containment , 1978 .

[20]  A. A. Amsden,et al.  A numerical fluid dynamics calculation method for all flow speeds , 1971 .

[21]  W. Herrmann,et al.  TOODY: A COMPUTER PROGRAM FOR CALCULATING PROBLEMS OF MOTION IN TWO DIMENSIONS. , 1967 .

[22]  W R Wise,et al.  EXPLOSION CONTAINMENT LAWS FOR NUCLEAR REACTOR VESSELS , 1965 .