Published 1977 | Version v1
Report Restricted

Program for alloy development for irradiation performance in fusion reactors

Creators

Description

The use of fission reactors as irradiation test facilities for structural materials for a fusion environment is discussed. A comparison is made of displacement damage and helium production in fast fission and fusion reactors for stainless steel

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01.

Files

Restricted

The record is publicly accessible, but files are restricted to users with access.

Additional details

Publishing Information

Imprint Pagination
7 p.
Report number
CONF-770523--10

Conference

Title
Symposium on neutron cross sections 10-40 MeV.
Dates
3 - 5 May 1977.
Place
Upton, New York, United States of America (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
8345220
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
MATERIALS TESTING; NEUTRON FLUX; PHYSICAL RADIATION EFFECTS; PLANNING; RESEARCH PROGRAMS; STAINLESS STEELS; THERMONUCLEAR REACTOR MATERIAL
Descriptors DEC
ALLOYS; CARBON ADDITIONS; CHROMIUM ALLOYS; CORROSION RESISTANT ALLOYS; IRON ALLOYS; IRON BASE ALLOYS; RADIATION EFFECTS; RADIATION FLUX; STEELS; TESTING; TRANSITION ELEMENT ALLOYS