Irradiation Effects in Pressure Vessel Materials for Steam-Cooled Fast Reactors / M. Grounes, P. Lindhagen

Conference Author:: Irradiation Effects in Structural Alloys for Thermal and Fast Reactors (1968 : San Francisco, Calif.)
Physical Description:: 1 online resource (24 pages) : illustrations, figures, tables
Additional Creators:: Grounes, M., Lindhagen, P., American Society for Testing and Materials, and ASTM International

Access Online

ezaccess.libraries.psu.edu

Availability

Finding items...

Restrictions on Access:

Subscription required for access to full text.
License restrictions may limit access.

Summary:

Steam-cooled fast reactor pressure vessels must withstand high pressures (130¿̐ư230 atm) and high neutron doses, for example, 5 ¿̐ư 10 20 n/cm 2 (>1 MeV). Two new steels have been investigated, a 16 Cr-5 Ni-1 Mo steel (Avesta 248 SV) and a 13 Cr-6 Ni-1.5 Mo steel (Bofors 2 RMO). Their tensile strengh is above 70 kg/mm2 at 300 C. The steels are unusually tough at low temperatures, and there is no sharp brittle-to-ductile transition. Various properties of the steels are described.

Dates of Publication and/or Sequential Designation:

Volume 1969, Issue 457 (January 1969)

Subject(s):

Other Subject(s):

ISBN:

9780803160361 (e-ISBN)
9780803161900
0803161905

Digital File Characteristics:

text file PDF

Bibliography Note:

Includes bibliographical references 22.

Other Forms:

Also available online via the World Wide Web. Tables of contents and abstracts freely available; full-text articles available by subscription.
Full text article also available for purchase.
Also available in PDF edition.

Reproduction Note:

Electronic reproduction. W. Conshohocken, Pa. : ASTM International, 1969. Mode of access: World Wide Web. System requirements: Web browser. Access may be restricted to users at subscribing institutions.

Technical Details:

Mode of access: World Wide Web.

Source of Acquisition:

ASTM International PDF Purchase price USD25.

View MARC record | catkey: 28002485