Analysis and extension of the SAND-II code in damage function unfolding applications. [BWR; PWR]
Conference
·
OSTI ID:6563725
A way has been found to include a-priori information about the expected energy dependence of the damage function (together with uncertainties) as part of the data input of the SAND-II code in damage function unfolding procedures. Damage function analysis is useful when it is necessary to predict property change in a spectrum that is different from the spectra which were used to develop information about the degradation characteristics of the material. If the damage is a non-linear function of fluence, it is sometimes necessary to define an intermediate degradation parameter which is linear in the fluence. The integral equations can then be replaced by a set of linear equations with finite widths for the energy groups and a fixed number of groups. The inclusion of the a-priori information about the damage function causes the linear equations set to be overdetermined. If this overdetermined set is regarded as a least squares problem in log-normal statistics, then a solution can be obtained by a method of steepest descent. The steepest descent solution-algorithm is similar but not identical to the basic algorithm of the SAND-II code. In an overdetermined case, the basic SAND-II algorithm is shown to iterate towards a solution which is identical to the log-normal least squares solution.
- Research Organization:
- Westinghouse Hanford Co., Richland, WA (USA)
- DOE Contract Number:
- EY-76-C-14-2170
- OSTI ID:
- 6563725
- Report Number(s):
- HEDL-SA-1475; CONF-780722-5
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
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Light-Water Moderated
Nonboiling Water Cooled
36 MATERIALS SCIENCE
360106 -- Metals & Alloys-- Radiation Effects
ALLOYS
BWR TYPE REACTORS
COMPUTER CODES
CONTAINERS
DAMAGING NEUTRON FLUENCE
DATA ANALYSIS
DATA PROCESSING
ENERGY DEPENDENCE
IRON ALLOYS
IRON BASE ALLOYS
NEUTRON FLUENCE
PHYSICAL RADIATION EFFECTS
PRESSURE VESSELS
PROCESSING
PWR TYPE REACTORS
RADIATION EFFECTS
REACTOR MATERIALS
REACTORS
S CODES
SPECTRA UNFOLDING
STEELS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
36 MATERIALS SCIENCE
360106 -- Metals & Alloys-- Radiation Effects
ALLOYS
BWR TYPE REACTORS
COMPUTER CODES
CONTAINERS
DAMAGING NEUTRON FLUENCE
DATA ANALYSIS
DATA PROCESSING
ENERGY DEPENDENCE
IRON ALLOYS
IRON BASE ALLOYS
NEUTRON FLUENCE
PHYSICAL RADIATION EFFECTS
PRESSURE VESSELS
PROCESSING
PWR TYPE REACTORS
RADIATION EFFECTS
REACTOR MATERIALS
REACTORS
S CODES
SPECTRA UNFOLDING
STEELS
WATER COOLED REACTORS
WATER MODERATED REACTORS