Thermal expansion coefficient of steels used in LWR vessels
- 1. University of Idaho, 1776 Science Center Drive, Idaho Falls, ID 83402 (United States)
- 2. Idaho National Laboratory, P.O. Box 1625, MS 3840, Idaho Falls, ID 83415 (United States)
Description
Because of the impact that melt relocation and vessel failure have on subsequent progression and associated consequences of a light water reactor (LWR) accident, it is important to accurately predict the heat-up and relocation of materials within the reactor vessel and heat transfer to and from the reactor vessel. Accurate predictions of such heat transfer phenomena require high temperature thermal properties. However, a review of vessel and structural steel material properties in severe accident analysis codes reveals that the required high temperature material properties are extrapolated with little, if any, data above 700 deg. C. To reduce uncertainties in predictions relying upon this extrapolated high temperature data, new thermal expansion data were obtained using pushrod dilatometry techniques for two steels used in LWR vessels: SA 533 Grade B, Class 1 (SA533B1) low alloy steel, which is used to fabricate most US LWR reactor vessels; and Type 304 stainless steel (SS304), which is used in LWR vessel piping, penetration tubes, and internal structures. This paper summarizes the new data and compares it to existing, lower temperature data in the literature
Availability note (English)
Available from http://dx.doi.org/10.1016/j.jnucmat.2008.02.088Additional details
Identifiers
- DOI
- 10.1016/j.jnucmat.2008.02.088;
- PII
- S0022-3115(08)00170-0;
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 376
- Journal Issue
- 2
- Journal Page Range
- p. 211-215
- ISSN
- 0022-3115
- CODEN
- JNUMAM
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 40002113
- Subject category
- S36: MATERIALS SCIENCE;
- Descriptors DEI
- DILATOMETRY; HEAT TRANSFER; LOW ALLOY STEELS; REACTOR VESSELS; STAINLESS STEEL-304; TEMPERATURE RANGE 0400-1000 K; THERMAL EXPANSION; THERMODYNAMIC PROPERTIES; WATER COOLED REACTORS; WATER MODERATED REACTORS
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; CONTAINERS; CORROSION RESISTANT ALLOYS; ENERGY TRANSFER; EXPANSION; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; NICKEL ALLOYS; PHYSICAL PROPERTIES; REACTORS; STAINLESS STEELS; STEEL-CR19NI10; STEELS; TEMPERATURE RANGE; THERMAL ANALYSIS; TRANSITION ELEMENT ALLOYS
Optional Information
- Copyright
- Copyright (c) 2008 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.