Development of Creep Constitutive Equation for Low-Alloy Steel
- 1. Seoul National University (Korea, Republic of)
- 2. Korea Atomic Energy Research Institute (Korea, Republic of)
- 3. Sandia National Laboratories (United States)
Description
High-temperature creep tests were performed with an SA533B1 low-alloy steel under both constant load and constant stress conditions. Using the measured minimum creep strain rates as a function of stress and temperature, least-square fittings were made into a Bailey-Norton-type power law equation. Based on the constant stress test results, a constitutive equation was developed for steady-state creep. The constitutive equation was then implemented in elastic-viscoplastic analysis of the lower head of a pressurized water reactor's reactor pressure vessel using a commercial FEM code named ABAQUS 5.8. The FEM model was validated using measured data from the lower head failure experiment conducted at the Sandia National Laboratories. The FEM model using the creep constitutive equation was shown to be capable of accurately predicting the lower head deformation behavior. Additional work, however, is needed to rationalize apparent inconsistency between the constant load data and constant stress data
Additional details
Identifiers
Publishing Information
- Journal Title
- Nuclear Technology
- Journal Volume
- 143
- Journal Issue
- 3
- Journal Page Range
- p. 347-357
- ISSN
- 0029-5450
- CODEN
- NUTYBB
INIS
- Country of Publication
- United States
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 38011628
- Subject category
- S42: ENGINEERING;
- Descriptors DEI
- CREEP; DEFORMATION; EQUATIONS; FAILURES; FINITE ELEMENT METHOD; LEAST SQUARE FIT; LOW ALLOY STEELS; PRESSURE VESSELS; PWR TYPE REACTORS; SANDIA NATIONAL LABORATORIES; STEADY-STATE CONDITIONS; STRAIN RATE; STRESSES
- Descriptors DEC
- ALLOYS; CALCULATION METHODS; CARBON ADDITIONS; CONTAINERS; ENRICHED URANIUM REACTORS; IRON ALLOYS; IRON BASE ALLOYS; MATHEMATICAL SOLUTIONS; MAXIMUM-LIKELIHOOD FIT; MECHANICAL PROPERTIES; NATIONAL ORGANIZATIONS; NUMERICAL SOLUTION; POWER REACTORS; REACTORS; STEELS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; US DOE; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2006 American Nuclear Society (ANS), United States, All rights reserved. http://epubs.ans.org/