Published 2009 | Version v1
Report

Utilization of multiscale experimental and computational techniques for the design of radiation-resistant steels

  • 1. University of California at Los Angeles, Los Angeles, CA 90095 (United States)
  • 2. Oak Ridge National Laboratory, Oak Ridge, TN (United States)

Description

Full text: Significant progress has been achieved in the operational performance and radiation resistance of ferritic-martensitic steels during the past few decades. Conventional high temperature steels, such as HT-9 and 2 1/4 Cr-1Mo have evolved into super Oxide Dispersion Strengthened (ODS) steels through successive optimization to meet strict performance and radiation-resistance constraints. Such evolution was possible through a combination of experimentation, modeling and empirical information. Further development and optimization of structural steels in nuclear applications will require full utilization of the available array of sophisticated experimental techniques and multiscale computational modeling, in addition to empirical data. We present here a systematic approach to the process of optimum steel development, by linking material fabrication to thermo-mechanical properties through a physical understanding of microstructure evolution. The optimization process is based on the application of design constraints (e.g. low activation, low DBTT, low swelling, creep resistance, and weldability) to describe the required microstructures, which in turn, can be controlled through material processing techniques. Prospects for future design of optimum structural steels in nuclear applications by utilization of the hierarchy of multiscale experimental and computational strategies will be described. (author)

Part of:
Book of abstracts of the joint EC-IAEA topical meeting on development of new structural materials for advanced fission and fusion reactor systems

Additional details

Publishing Information

Imprint Title
Book of abstracts of the joint EC-IAEA topical meeting on development of new structural materials for advanced fission and fusion reactor systems
Imprint Pagination
57 p.
Journal Page Range
p. 14
Report number
INIS-XA--09N1744

Conference

Title
Joint EC-IAEA topical meeting on development of new structural materials for advanced fission and fusion reactor systems
Dates
5-9 Oct 2009
Place
Barcelona (Spain)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
40109399
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CREEP; DESIGN; DISPERSIONS; FABRICATION; FERRITIC STEELS; MARTENSITIC STEELS; MICROSTRUCTURE; OPTIMIZATION; PERFORMANCE; SIMULATION; SWELLING; WELDABILITY
Descriptors DEC
ALLOYS; CARBON ADDITIONS; DEFORMATION; IRON ALLOYS; IRON BASE ALLOYS; MECHANICAL PROPERTIES; STEELS; TRANSITION ELEMENT ALLOYS

Optional Information

Notes
Keynote paper
Secondary number(s)
F1-TR--37435