Charpy trend-curve development based on PWR surveillance date
Conference
·
OSTI ID:5053508
The formulas given in the text provide a useful method of predicting the irradiation induced increase in the 41 joule Charpy transition temperature for plate and weld material. The standard deviations for the least squares fits are 26.4/sup 0/F for the weld equation and 15.6/sup 0/F for the plat relationship. The current method of derivation produces an unbiased estimate of the fluence exponent, resulting in increased reliability for fluence extrapolations. The method given for error estimation provides a relatively rigorous procedure for calculating uncertainties and takes proper account of the effects of uncertainties in the independent variables in any given application of the formulas. 11 refs., 4 figs., 4 tabs.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (USA)
- DOE Contract Number:
- AC06-76FF02170
- OSTI ID:
- 5053508
- Report Number(s):
- HEDL-SA-3011; CONF-8310143-74; ON: DE85018502
- Country of Publication:
- United States
- Language:
- English
Similar Records
Pressure-vessel-steel irradiation-embrittlement formulas derived for PWR surveillance data
Curve fitting and uncertainty analysis of Charpy impact data. [PWR; BWR]
Fractographic examination of ferritic alloy Charpy specimens at a fluence of 6 x 10/sup 22/ n/cm/sup 2/
Conference
·
Fri Dec 31 23:00:00 EST 1982
·
OSTI ID:5956329
Curve fitting and uncertainty analysis of Charpy impact data. [PWR; BWR]
Technical Report
·
Thu Dec 31 23:00:00 EST 1981
·
OSTI ID:5488333
Fractographic examination of ferritic alloy Charpy specimens at a fluence of 6 x 10/sup 22/ n/cm/sup 2/
Technical Report
·
Wed May 01 00:00:00 EDT 1985
·
OSTI ID:5680000
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
CHARPY TEST
CONTAINERS
COPPER
DESTRUCTIVE TESTING
ELEMENTS
FRACTURE PROPERTIES
IMPACT TESTS
JOINTS
MATERIALS
MATERIALS TESTING
MATHEMATICAL MODELS
MECHANICAL PROPERTIES
MECHANICAL TESTS
METALS
NEUTRON FLUENCE
NICKEL
PRESSURE VESSELS
PWR TYPE REACTORS
REACTOR MATERIALS
REACTORS
STRESS ANALYSIS
TESTING
THERMAL SHOCK
TRANSITION ELEMENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
CHARPY TEST
CONTAINERS
COPPER
DESTRUCTIVE TESTING
ELEMENTS
FRACTURE PROPERTIES
IMPACT TESTS
JOINTS
MATERIALS
MATERIALS TESTING
MATHEMATICAL MODELS
MECHANICAL PROPERTIES
MECHANICAL TESTS
METALS
NEUTRON FLUENCE
NICKEL
PRESSURE VESSELS
PWR TYPE REACTORS
REACTOR MATERIALS
REACTORS
STRESS ANALYSIS
TESTING
THERMAL SHOCK
TRANSITION ELEMENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS