Corrosion and hydriding of three zirconium alloys in N-Reactor process tube 0553
Coupons of three zirconium alloys - Zircaloy-2 (two lots and three metallurgical conditions); Zircaloy-4; and Zr-2.5Nb - were exposed in N-Reactor pressure tube 0553 for 155 days at 1.2 x 10/sup 20/ n/cm/sup 2/, >1 MeV. Although the exposure was relatively mild, significant differences in hydriding trends were observed for the three alloys. Hydriding rates differed for the three alloys: the rates were highest for Zircaloy-2, intermediate for Zircaloy-4, and lowest for Zr-2.5Nb. The corrosion rates for all three alloys were relatively low in the N-Reactor coolant. The temperatures at the in-flux and downstream out-of-flux locations were 250 to 258/sup 0/C (482 to 496/sup 0/F) and 260 to 268/sup 0/C (500 to 514/sup 0/F), respectively, which are lower than currently indicated for equivalent N-Reactor locations. The reactor was converting to steam production during the period of the test; but failure of a transformer delayed full steam operation until after the test was completed, which may explain the lower temperatures during the test.
- Research Organization:
- Pacific Northwest Lab., Richland, WA (USA)
- DOE Contract Number:
- AC06-76RL01857; AC06-76RL01830
- OSTI ID:
- 6303552
- Report Number(s):
- UNI-3251; PNL-5400; ON: DE87012223
- Country of Publication:
- United States
- Language:
- English
Similar Records
Oxidation of zirconium alloys in steam at 1000 to 1850/sup 0/C. [Steam at 1000/sup 0/ to 1850/sup 0/C]
EVALUATION OF ZIRCONIUM 1.5 W/O NIOBIUM CLADDING FOR USE IN BOILING WATER REACTOR ENVIRONMENTS
Related Subjects
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
36 MATERIALS SCIENCE
360105 -- Metals & Alloys-- Corrosion & Erosion
360106 -- Metals & Alloys-- Radiation Effects
ALLOYS
CHEMICAL REACTIONS
CHROMIUM ADDITIONS
CHROMIUM ALLOYS
COMPUTER CODES
COOLING SYSTEMS
CORROSION
DATA
ELEMENTS
ENERGY SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
ETR REACTOR
EXPERIMENTAL DATA
F CODES
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
HYDRIDATION
HYDROGEN
INFORMATION
IRON ADDITIONS
IRON ALLOYS
IRRADIATION
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
MECHANICS
NEUTRON FLUX
NONMETALS
NUMERICAL DATA
PHYSICAL RADIATION EFFECTS
PRESSURE TUBES
RADIATION EFFECTS
RADIATION FLUX
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
TIN ALLOYS
TUBES
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCALOY 2
ZIRCALOY 4
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS