Development of ferritic steels for reduced activation: the US program

Conference · Wed Jan 01 00:00:00 EST 1986

OSTI ID:5908459

Klueh, R L; Gelles, D S; Lechtenberg, T A

The Cr-Mo ferritic (martensitic) steels are candidates for the structural components of fusion reactors. Irradiation of such steels in a fusion environment produces long-lived radioactive isotopes, which lead to difficult radioactive waste disposal problems once the structure is removed from service. Such problems could be reduced by using steels that contain only elements that produce radioactive isotopes that decay to low levels in a reasonable time (tens of years instead of hundreds or thousands of years). The US Department of Energy has a program to develop steels to meet the criteria for shallow land burial as opposed to deep geologic storage. A review of the alloy development programs indicates that ferritic steels that meet these criteria can be developed.

• Research Organization: Oak Ridge National Lab., TN (USA); Hanford Engineering Development Lab., Richland, WA (USA); GA Technologies, Inc., San Diego, CA (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 5908459
• Report Number(s): CONF-860421-28; ON: DE86010025
• Resource Relation: Conference: 2. international conference on fusion reactor materials (ICFRM-2), Chicago, IL, USA, 13 Apr 1986; Other Information: Paper copy only, copy does not permit microfiche production
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
CHROMIUM ALLOYS
MATERIALS TESTING
FERRITIC STEELS
MOLYBDENUM ALLOYS
IRRADIATION
RADIOACTIVATION
THERMONUCLEAR REACTOR MATERIALS
ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
STEELS
TESTING
360106* - Metals & Alloys- Radiation Effects
700209 - Fusion Power Plant Technology- Component Development & Materials Testing