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Title: Prediction and Monitoring Systems of Creep-Fracture Behavior of 9Cr-1Mo Steels for Teactor Pressure Vessels

A recent workshop on next-generation nuclear plant (NGNP) topics underscored the need for research studies on the creep fracture behavior of two materials under consideration for reactor pressure vessel (RPV) applications: 9Cr-1Mo and SA-5XX steels. This research project will provide a fundamental understanding of creep fracture behavior of modified 9Cr-1Mo steel welds for through modeling and experimentation and will recommend a design for an RPV structural health monitoring system. Following are the specific objectives of this research project: Characterize metallurgical degradation in welded modified 9Cr-1Mo steel resulting from aging processes and creep service conditions; Perform creep tests and characterize the mechanisms of creep fracture process; Quantify how the microstructure degradation controls the creep strength of welded steel specimens; Perform finite element (FE) simulations using polycrystal plasticity to understand how grain texture affects the creep fracture properties of welds; Develop a microstructure-based creep fracture model to estimate RPVs service life; Manufacture small, prototypic, cylindrical pressure vessels, subject them to degradation by aging, and measure their leak rates; Simulate damage evolution in creep specimens by FE analyses; Develop a model that correlates gas leak rates from welded pressure vessels with the amount of microstructural damage; Perform large-scale FE simulations with a realisticmore » microstructure to evaluate RPV performance at elevated temperatures and creep strength; Develop a fracture model for the structural integrity of RPVs subjected to creep loads; and Develop a plan for a non-destructive structural health monitoring technique and damage detection device for RPVs.« less
Authors:
 [1] ;  [1] ;  [1] ;  [1]
  1. Univ. of Idaho, Moscow, ID (United States)
Publication Date:
OSTI Identifier:
1110643
Report Number(s):
DOE/NEUP--09-835
TRN: US1600899
DOE Contract Number:
AC07-05ID14517
Resource Type:
Technical Report
Research Org:
Univ. of Idaho, Moscow, ID (United States)
Sponsoring Org:
USDOE, Nuclear Energy University Programs (NEUP)
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; CHROMIUM-MOLYBDENUM STEELS; CREEP; FRACTURES; PRESSURE VESSELS; WELDED JOINTS; MICROSTRUCTURE; FINITE ELEMENT METHOD; NUCLEAR POWER PLANTS; MONITORING; DAMAGE; CYLINDERS; FRACTURE PROPERTIES; SERVICE LIFE; AGING; FORECASTING; LEAKS; PLASTICITY; SIMULATION; DESIGN; PERFORMANCE; TEXTURE; DYNAMIC LOADS