Published 1993 | Version v1
Book Metadata-only

Application of miniature tension specimens to studies of radiation damage in metals

Creators

  • 1. Pacific Northwest Lab., Richland, WA (United States)
  • 2. Univ. of Missouri, Rolla, MO (United States)

Description

Miniature sheet-type tension specimens are currently being used in a variety of radiation damage studies conducted in a number of different reactors. Although these specimens are very small (12.7 mm long, 0.25 mm thick, 1.0 mm gage width), they have proven successful in addressing issues encountered in both thermal reactors and anticipated fusion reactors. This paper reviews the results of a number of recent studies that illustrate the range of applicability of these small specimens. When combined with other types of specimens and other types of measurements made prior to tension testing, miniature tension specimens have been found to serve as very useful tools for application to both fundamental studies and alloy screening studies. 62 refs., 13 figs

Part of:
Small specimen test techniques applied to nuclear reactor vessel thermal annealing and plant life extension

Additional details

Publishing Information

Publisher
American Society for Testing and Materials.
Imprint Place
Philadelphia, PA (United States)
ISBN
0-8031-1869-4
Imprint Title
Small specimen test techniques applied to nuclear reactor vessel thermal annealing and plant life extension
Imprint Pagination
468 p.
Journal Page Range
p. 336-355.

Conference

Title
American Society for Testing and Materials (ASTM) international symposium on small specimen test techniques applied to nuclear reactor vessel thermal annealing and plant life extension.
Dates
29-31 Jan 1992.
Place
New Orleans, LA (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
26001737
Subject category
S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ALLOYS; DATA; FFTF REACTOR; MATERIALS TESTING; MECHANICAL PROPERTIES; MECHANICAL TESTS; MICROSTRUCTURE; PHYSICAL RADIATION EFFECTS; PRESSURE VESSELS; REACTOR MATERIALS; SAMPLE PREPARATION; THERMONUCLEAR REACTOR MATERIALS
Descriptors DEC
CONTAINERS; CRYSTAL STRUCTURE; EPITHERMAL REACTORS; FAST REACTORS; INFORMATION; LIQUID METAL COOLED REACTORS; MATERIALS; RADIATION EFFECTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SODIUM COOLED REACTORS; TEST FACILITIES; TEST REACTORS; TESTING

Optional Information

Secondary number(s)
CONF-920146--.