ANALYSIS OF PWR FUEL ROD DEVELOPMENT PROCTESSES.

Technical Report · Mon Nov 01 04:00:00 EST 1954

OSTI ID:4327850

Goodwin, J G; Richards, E L; Snyder, H J; Thombaugh, R W

An analysis is presented of the processes and methods which are considered to be the best so far developed for fabrication of Pressurized Water Reactor fuel rods. In brief, the process for producing the fuel rod will start with the as-cast raw materials which wiil be fabricated into coextrusion billets by the most expedient process. The billets will be extruded to a relatively large diameter and then finished to a final diameter in the most efficient manner possible to provide the fuel rod stock. In many instances the assumptions and calculations used in making the numerous recommendations are given. The process and methods have been developed to produce a clad fuel rod having a final diameter of about 0.300 in. with a Zircaloy2 cladding thickness of 0.030 in. The fuel alloy used is nominally l2 wt. % Mo in natural U. Cost and fabrication analysis for Zircaloy-2 billet components is presented. (L.T.W.)

• Research Organization: Westinghouse Electric Corp. Atomic Power Div., Pittsburgh
• DOE Contract Number: AT(11-1)-GEN-14
• NSA Number: NSA-12-002151
• OSTI ID: 4327850
• Report Number(s): WAPD-MDM-19
• Country of Publication: United States
• Language: English

Related Subjects

ALLOYS
CANNING
CASTING
ECONOMICS
EXTRUSION
FABRICATION
FUEL ELEMENTS
MOLYBDENUM
NATURAL URANIUM FUEL
NUMERICALS
PHYSICS
PRESSURE
PWR
REACTORS
RODS
WATER COOLANT
ZIRCALOY