Materials and structures technology program plan for advanced reactors: Program plan, FY 1988--1993
To satisfy the long-term needs of the United States for electric power, the strategy of the Department of Energy (DOE) includes development of advanced liquid metal reactor (LMR) plants as a low-cost, low-risk, nuclear power option. These plants will have passive safety features, such as self-actuated shutdown and natural-convection decay heat removal, and will employ modular construction techniques. Compared to current light-water reactor (LWR) plants, the advanced LMR plants offer benefits including (1) enhanced safety and licensability, (2) increased reliability and availability, (3) improved economics and (4) increased US competitiveness in the international marketplace. As part of the DOE Advanced LMR Program, conceptual design was completed for two plants, the Power Reactor Inherently Safe Module (PRISM) by the General Electric Company (GE), and the Sodium Advanced Fast Reactor (SAFR) by Rockwell International Corporation (RI). PRISM was selected as the reference concept, and advanced conceptual design GE is scheduled for FY 1989--91. Advanced LMR plants will be designed for a service life of up to 60 years. Such long service presents significant challenges to the structural integrity of the reactor and the heat transport systems. These challenges arise not only from the relatively high service temperatures but also from the large, rapid temperature changes associated with the use of a liquid metal as the heat transport medium. An effective response to this unique set of challenges is required to ensure the success of the DOE Advanced LMR Program. For this reason, the DOE Office of Technology Support Programs established a coordinated program to develop the specialized high-temperature materials and structural design technology necessary for safe and reliable, long-term operation of advanced LMR plants. This Program Plan describes the activities required to complete the development of this technology.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6535845
- Report Number(s):
- DOE/OR-896; ON: DE89005954
- Resource Relation:
- Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
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PROGRAM MANAGEMENT
REACTOR MATERIALS
MATERIALS TESTING
STAINLESS STEELS
STEELS
AGING
COORDINATED RESEARCH PROGRAMS
COST
CRACKS
CREEP
DEFORMATION
DESIGN
ECONOMICS
FAILURES
FATIGUE
LEAKS
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MECHANICAL STRUCTURES
RADIATION EFFECTS
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TECHNOLOGY ASSESSMENT
TEMPERATURE EFFECTS
US DOE
WELDED JOINTS
ALLOYS
BREEDER REACTORS
DATA PROCESSING
EPITHERMAL REACTORS
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FBR TYPE REACTORS
HIGH ALLOY STEELS
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
LIQUID METAL COOLED REACTORS
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MATERIALS
NATIONAL ORGANIZATIONS
PROCESSING
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