Multivariable modeling of J-R data
Creators
- 1. Modeling and Computing Services, Newark, CA (United States)
Description
Current methods for evaluating safety and remaining life issues for reactor pressure vessels (RPV's) and piping are based on the J-R curve. Unfortunately, field-aged J-specimens are not always available for the specific weld or heat in service or at the radiation conditions which match the case to be analyzed. In order to best evaluate plant safety, therefore, it is necessary to reliably estimate a J-R curve from available data, such as material chemistry, radiation exposure, tensile properties, and Charpy data. A multivariable model for predicting J-R curves from available data, such as material chemistry, radiation exposure, and Charpy data, is being developed. This is an interim report on a project to collect public test data, apply advanced pattern recognition tools, and fit an improved model. A four-parameter model for the dependence of Jd on crack extension, Charpy energy, temperature, and specimen thickness is presented
Additional details
Publishing Information
- Imprint Title
- Eighteenth water reactor safety information meeting. Volume 3, Pressure vessel integrity; Piping and NDE; Aging and components: Proceedings
- Imprint Pagination
- 574 p.
- Journal Page Range
- p. 55-70.
- Report number
- NUREG/CP--0114-Vol.3
Conference
- Title
- 18. water reactor safety information meeting.
- Dates
- 22-24 Oct 1990.
- Place
- Rockville, MD (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24038745
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; CHARPY TEST; CRACK PROPAGATION; CRACKS; DATA BASE MANAGEMENT; FRACTURE MECHANICS; FRACTURE PROPERTIES; LEAST SQUARE FIT; MATHEMATICAL MODELS; NEUTRON FLUENCE; NONLINEAR PROBLEMS; PHYSICAL RADIATION EFFECTS; PIPES; PRESSURE VESSELS; PRESSURIZATION; PWR TYPE REACTORS; REACTOR SAFETY; RESEARCH PROGRAMS; STAINLESS STEELS; TEMPERATURE DEPENDENCE; THERMAL SHOCK; WELDED JOINTS
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CONTAINERS; DESTRUCTIVE TESTING; ENRICHED URANIUM REACTORS; HIGH ALLOY STEELS; IMPACT TESTS; IRON ALLOYS; IRON BASE ALLOYS; JOINTS; MANAGEMENT; MATERIALS TESTING; MAXIMUM-LIKELIHOOD FIT; MECHANICAL PROPERTIES; MECHANICAL TESTS; MECHANICS; NUMERICAL SOLUTION; POWER REACTORS; RADIATION EFFECTS; REACTORS; SAFETY; STEELS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-9010185--Vol.3.