PRESSURIZED WATER REACTOR PROGRAM TECHNICAL PROGRESS REPORT FOR THE PERIOD SEPTEMBER 9 TO OCTOBER 20, 1955
Progress in the design, development, and construction of PWR power plant systems and components and PWR core and auxiliaries is summarized. The blanket assembly design is described and illustrated. Results of MTR evaluation of fuel element failure instrumentation are reported. Development of fabrication and testing tochaiques for clad fuel elements, fuel rods, plates, and assemblies is described. Investigations of fuel and cladding alloys include crystal structure and thermal stability determinations on U--Mo alloys, studies on the nature of the hydride phase formed during corrosion of gamma -phase alloys in high- temperature water, and specific heat, resistivity, and phase diagram studies of U- -Mo and U--Nb alloys. The equilibrium and kinetics in the system UO/sub 2/--O/ sub 2/ are being studied to gain information on the structure and stability of UO/ sub 2/ under various conditions. Results of irradiation tests on UO/sub 2/ samples and of thermal cycling tests of Zircaloy-2 clad UO/sub 2/ rods are reported. Corrosion test resuIts are summarized for unclad and Zircaloy-2 clad U- - Mo and U--Nb samples. The radiation induced volume change of prototype fuel reds has been investigated. Studies of the fabrication cladding, tensile properties, and corrosion of U-- Si systems are described. Corrosion tests are continuing on Zircaloy-2 clad U-- Zr fuel elements and on various experimental Al alloys for cladding applications. Work was continued on the preparation, corrosion and sinterability of pure UO/sub 2/ and UO/sub 2/ containing additives. Operation and chemical analysis of in-pile loop experiments are described. Results are reported from studies of the erosion of UO/sub 2/ in high-velocity coolant, decontamination of water by ion exchange resins, sorption of radioisotopes on stainless steel, and decontamination of corrosion loops. Work in reactor physics has included PWR control calculations using a 2-dimensional UNIVAC code, calculation of fission product activity in the primary coolant, and criticaiity studies on the Flexibie Critical Experiment and on a lattice of UO/ sub 2/ fuel reds in the TRX. Current PWR plant parameters are recapitulated. (D.E.B.)
- Research Organization:
- Westinghouse Electric Corp. Atomic Power Div., Pittsburgh
- DOE Contract Number:
- AT-11-1-GEN-14
- NSA Number:
- NSA-12-007480
- OSTI ID:
- 4327739
- Report Number(s):
- WAPD-MRP-57(Rev.)
- Resource Relation:
- Other Information: Decl. Mar. 16, 1957. Orig. Receipt Date: 31-DEC-58
- Country of Publication:
- United States
- Language:
- English
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