PRESSURIZED WATER REACTOR (PWR) PROJECT TECHNICAL PROGRESS REPORT FOR THE PERIOD JUNE 24, 1959 TO AUGUST 23, 1959

Technical Report · Sat Oct 31 04:00:00 EST 1959

OSTI ID:4222618

A three-dimensional study of core power distribution as a function of lifetime resulted in the adoption of new safety shutdown set points for the reactor protection system during the latter portion of core life. Feasibility studies to identify necessary plant modifications and power plant problems associated with 150 Mw operation of core 2 were completed. The most probable source of Po in the PWR primary system was determined to be fuel element surface contamination by bismuth. The effectiveness of alkaline permanganate -ammonium citrate solution for removing activated corrosion products from surfaces was found to be velocity dependent. Results of thermal and hydraulic analysis of core 2 were used to establish core design parameters pertaining to 150 Mw(w) operation. The feasibility of longitudinal and transverse welding techniques was established and data on diffusion bonding are presented. Preliminary data on electrical resistance changes after irradiation and in-pile annealing of B/sup 10/ bearing matrices, and on fission fragment damage in ceramics are presented. Data indicate that thermal capabilities of UO/sub 2/ fuel elements are affected by the gap between pellets and cladding. Post irradiation burst testing and fusion gas release measurements of oxide plates indicate littie deterioration of oxide plate fuel elements. The feasibility of pressure bonding oxide plates was established. Data on self-diffusion coefficients in UO/sub 2/ at 1600 and 1675 deg C are presented. Results of threedimensional depletion analysis of PWR-1 through Seed 2 reactivity life indicate a 1000 EFPH longer life than that for Seed 1. Detailed and gross neutron measurements in a 248 kg PWR-2 mock-up were made to determine the radial peaking factors and power sharing between seed and blanket. Also the one-rod stuck shutdown margin was examined in a 245 kg PWR-2 mock-up to determine the effects of changes in control rod span blade thickness, rod material, poison lamp sizes, and lump location in the assembly. Resonance self-shielding in P/sup 239/ and Pu/sup 240/ is being incorporated in the theoretical calculations of reactivity which is compared with the experimental reactivity obtained in the long term reactivity gains program (For preceding period see WAPD-MRP-80.) (J. R.D.)

• Research Organization: Westinghouse Electric Corp. Bettis Atomic Power Lab., Pittsburgh
• DOE Contract Number: AT(11-1)-GEN-14
• NSA Number: NSA-13-023119
• OSTI ID: 4222618
• Report Number(s): WAPD-MRP-81
• Country of Publication: United States
• Language: English

Related Subjects

ABSORPTION-- CONTROL ELEMENTS-- MOCKUP-- PLATES-- PRESSURE-- PWR-- QUANTITATIVE ANALYSIS-- REACTORS-- RODS-- SHUTDOWN-- THICKNESS-- VARIATIONS-- WATER COOLANT-- WATER MODERATOR
ABSORPTION-- MATHEMATICS-- MEASURED VALUES-- NEUTRONS-- PLUTONIUM 239-- PLUTONIUM 240-- PRESSURE-- PWR-- REACTIVITY-- REACTORS-- RESONANCE-- WATER COOLANT-- WATER MODERATOR
BEARINGS-- BORON 10-- CANNING-- CERAMICS-- DEFECTS-- ELECTRIC CONDUCTIVITY-- FISSION PRODUCTS-- FUEL ELEMENTS-- IN PILE LOOPS-- IRRADIATION-- MECHANICAL STRUCTURES-- PELLETS-- PRESSURE-- PWR-- REACTORS-- URANIUM DIOXIDE-- VARIATIONS-- WATER COOLANT-- WATER MODERATOR
BISMUTH-- CONTAMINATION-- COOL
REACTORS