STUDIES OF REACTOR CONTAINMENT. Bimonthly Progress Report, August- September 1963
Progress is reported on crushable shield analysis and design, shock impingemert experiments on crushable shields, and coolant decompression experiments and analysis. A description of the various subroutines used in generalized stress wave motion computer code written in the FORTRAN language for the IBM 7090 Computer for calculation of wave transmission in layered composites of materials is given along with their uses. A data acquisition method is described which uses data from successive shock tube loading experiments on one sample to obtain the unloading isentrope relations for balsa wood in the shock tube facility. Information is given regarding the initial stages of vapor formation caused by sudden decompression of water. (N.W.R.)
- Research Organization:
- Illinois Inst. of Tech., Chicago IIT Research Inst.
- NSA Number:
- NSA-18-009578
- OSTI ID:
- 4086945
- Report Number(s):
- IITRI-A6042-3
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
COOLANTS
DEFORMATION
DIGITAL SYSTEMS
EVAPORATION
FORTRAN
IBM 7090
IMPACT SHOCK
LAYERS
MATERIALS TESTING
MEASURED VALUES
MECHANICAL PROPERTIES
MECHANICAL STRUCTURES
NUMERICALS
PLANNING
POWER PLANTS
PRESSURE
PRODUCTION
PROGRAMMING
REACTOR SAFETY
REACTOR TECHNOLOGY
SHELLS
STABILITY
STRESSES
TENSILE PROPERTIES
TUBES
VAPORS
VARIATIONS
WOOD