CYGRO-2: a FORTRAN IV computer program for stress analysis of the growth of cylindrical fuel elements with fission gas bubbles (LWBR Development Program)
Technical Report
·
OSTI ID:6718657
The digital computer program CYGRO-2 provides a method of structural analysis for an oxide-fueled, metal clad rod-type fuel element in a pressurized environment. Stresses and strains are determined in a cross-section of fuel and clad undergoing thermal expansion and irradiation growth. Elastic, plastic, and creep parameters are used to calculate the effects of temperature, pressure, solid fission product growth, and gas bubble expansion. The axially symmetric fuel may have radial zones and a nonfissionable core or void. (NSA 21: 14114)
- Research Organization:
- Bettis Atomic Power Lab., Pittsburgh, PA (USA)
- DOE Contract Number:
- AT(11-1)-GEN-14
- OSTI ID:
- 6718657
- Report Number(s):
- WAPD-TM-547
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220300* -- Nuclear Reactor Technology-- Fuel Elements
BREEDER REACTORS
C CODES
COMPUTER CODES
CREEP
FISSION PRODUCTS
FLUIDS
FORTRAN
FUEL ELEMENTS
GASES
ISOTOPES
LWBR TYPE REACTORS
MECHANICAL PROPERTIES
PROGRAMMING LANGUAGES
RADIOACTIVE MATERIALS
REACTOR COMPONENTS
REACTORS
STRESS ANALYSIS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220300* -- Nuclear Reactor Technology-- Fuel Elements
BREEDER REACTORS
C CODES
COMPUTER CODES
CREEP
FISSION PRODUCTS
FLUIDS
FORTRAN
FUEL ELEMENTS
GASES
ISOTOPES
LWBR TYPE REACTORS
MECHANICAL PROPERTIES
PROGRAMMING LANGUAGES
RADIOACTIVE MATERIALS
REACTOR COMPONENTS
REACTORS
STRESS ANALYSIS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS