Supplement A to PT-IP-263-A-FP evaluation of chemically nickel plated fuel elements

Technical Report · Mon Jul 10 04:00:00 EDT 1961

DOI:https://doi.org/10.2172/10178385· OSTI ID:10178385

Clinton, M A

Irradiation of the initial test in this program involving ten tubes of alternately charged nickel-plated C-64 alloy clad test elements and X-8001 alloy control elements has been successfully completed. The test indicated that the nickel-plate spalling problem has been resolved as no significant spalling or flaking was observed during the post-irradiation examination. The second test in this program will be to verify the performance of nickel-plate with a pilot loading (up to 100 charges) of fuel elements which have been nickel-plated on a production basis. The objectives of this test are to demonstrate with a larger scale test that nickel-plate performs satisfactorily and that reducing the nominal plate thickness from .6 mil to .2 mil will not affect the performance of the nickel-plate fuel element. This test authorizes the irradiation of up to 100 columns of OIIN, chemically nickel-plated, C-64 alloy jacketed fuel elements to 200% of normal goal exposure to extend the evaluation of nickel-plated fuel elements on a pilot scale at DR Reactor. Seventy columns will be plated to a nominal thickness of .6 mil and thirty columns to a nominal .2 mil thickness. Twenty measured columns, ten representing each plate thickness, will be charged to monitor the irradiation performance. Effluent samples will be obtained during the course of the test from a pair of tubes, each tube containing a measured monitor charge representing each plate thickness.

• Research Organization: General Electric Co., Richland, WA (United States). Hanford Atomic Products Operation
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 10178385
• Report Number(s): HW--64419-F; ON: DE94018022
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210300
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600
CORROSION RESISTANCE
FUEL ELEMENTS
HANFORD PRODUCTION REACTORS
HISTORICAL ASPECTS
PERFORMANCE TESTING
POWER REACTORS
NONBREEDING
GRAPHITE MODERATED
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS