Alloy Development Program. Quarterly technical progress letter, October, November, December 1976

Technical Report · Thu Mar 31 23:00:00 EST 1977

DOI:https://doi.org/10.2172/709477· OSTI ID:709477

Laidler, J J ^[1]

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1. comp.

Progress is reported in six chapters: swelling and creep, analytical studies (of irradiation effects), coolant compatibility (sodium), and status of EBR-II irradiation tests (one table). Materials studied include HT-9, 330 ss, Inconel 706, A-286, Nimonic PE16, Inconel 718, 310 ss, various developmental alloys, and 316 ss. Nickel ions as well as reactor irradiations were used in the studies of radiation effects. (212 figs., 54 tables). (DLC)

• Research Organization: Hanford Engineering Development Lab., Richland, WA (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: AC06-76FF02170
• OSTI ID: 709477
• Report Number(s): HEDL-TC--160-11
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
ALLOY-A-286
ALLOY-HT-9
CORROSION
CORROSIVE EFFECTS
EBR-2 REACTOR
INCONEL 706
INCONEL 718
ION BEAMS
IRRADIATION
LMFBR TYPE REACTORS
NEUTRON BEAMS
NICKEL IONS
NIMONIC PE16
PERFORMANCE TESTING
PHYSICAL RADIATION EFFECTS
REACTOR MATERIALS
RESEARCH PROGRAMS
SODIUM
STAINLESS STEEL-310
STAINLESS STEEL-316
STAINLESS STEEL-330