PRESSURIZED WATER REACTOR (PWR) PROJECT TECHNICAL PROGRESS REPORT FOR THE PERIOD FEBRUARY 24, 1961 TO APRIL 23, 1961

Technical Report · Tue Oct 31 04:00:00 EST 1961

OSTI ID:4046740

; 6 ; : 8 9 7 < H 8 8 < 7 : 6 9 9 9 lated with a revised analytical model and is found to remain relatively constant through seed life. A redefinition of the fuel zone boundaries in the Core 2 seed cluster design was recommended to reduce local power peaks in the seed, and consequently, improve seed power capability. A study was initiated to revise the Core 2 mechanical hot channel factors associated with fuel dimensions and concentration to take advantage of random variations. Modifications were made to the mechanical design and instrumentation. Initial tests of the blanket assembly FEDAL sampling rake were completed. Fatigue testing of PWR-2-compartmented blanket-fuel plate cladding was resumed, using isostatic-pressure-bonded plates. General approval was received for the conceptual design of the electromechanical system for driving neutron sensitive wires into the six core-flux thimbles. The relative temperatures of the clad and fuel materials in Core 2 fuel elements, during quenching after beta heat treatment, were calculated to confirm conditions necessary for forming clearance volumes within the fuel compartments. In the compaction of blanket fuel wafers, end cracking was eliminated by modifications to the die. Improved adherency of the pyrolytic carbon coating on blanket wafers was obtained. The production of seed wafers was hampered by problems of contamination and an inability to produce a consistent isotopic content. Based on the results of the program to fabricate 21 half-length blanket fuel elements, it was recommended that a release be granted for fabrication of 10% of the Core 2 blanket fuel elements. Acceptable bonds were produced on plates containing the boron steel, poison wafers. An interim beta treating facility was installed. Plant Modification for Core 2. Design report on the utilization of the FEDAL sample piping for safety injection was submitted to the AEC. The design report on FEDAL operation, including integration with safety injection was also submitted. A recommendation for additional boiler steam relief valves was resubmitted. An evaluation of the adequacy of the neutron shield tank for Core 2 operation was submitted. Technical approval was received for the PWR Emergency Plan Drill procedures on minor airborne and waterborne release of radioactivity. Design drawings for the "AC" Rod Drive Static Inverter Prototype were approved. Specification for the Nuclear-Protection System was approved and released for quotations. The study of Turbine Heat Dissipation System interaction was completed. The Data Computer for the PWR Data Acquisition System was delivered to the Shippingport Site. Metallurgy of Core Materials. In-pile thermal conductivity measurements on UO/sub 2/, ZrO/sub 2/ + 34 wt.% UO/sub 2/, and ZrO/ sub 2/ + 46 wt.% UO/sub 2/ were obtained for irradiations up to about 5 x lO/sup 2//sup 0/ fissions/cc. Samples of ZrO/sub 2/ + 34 wt.% UO/sub 2/ and ZrO/sub 2/ + 46 wt.% UO/sub 2/ were irradiated to-36 1 x lO/sup 2//sup 0/ and 41 6 x lO/sup 2//sup 0/ fissions/cc, respectively, and measurements of swelling were obtained. The results confirm design parameters presently in use for Core 2. Metallographic examination of ZrO/sub 2/ + 46 wt.% UO/sub 2/ irradiated to 23.6 x 10/sup 2// sup 0/ and 27.4 x lO/sup 2//sup 0/ fissions/cc showed the presence of small, spherical white particles which appear to be associated with regions of large porosity. Excellent bond quality of betatreated blanket and seed oxide plates was obtained at bonding temperatures of 1550 to 1575 deg F and 1600 to 1625 deg F. A process was developed for applying adherent graphite-sprayed coatings to chromium-plated, borated stainless steel poison inserts. Impurity contamination causing formation of "white spot" inclusions in unirradiated sintered seed fuel wafers was found to be tramp iron introduced into the seed fuel during the crushing and size reduction steps in the fabrication process. Reactor Physics. A series- of zero power physics tests were performed following 6140 EFPH of PWR Core 1 Seed 2 operation at Shippingport. A proposal was

• Research Organization: Westinghouse Electric Corp. Bettis Atomic Power Lab., Pittsburgh
• DOE Contract Number: AT(11-1)-GEN-14
• NSA Number: NSA-15-021843
• OSTI ID: 4046740
• Report Number(s): WAPD-MRP-91
• Country of Publication: United States
• Language: English

Related Subjects

BONDING
BORATES
CHROMIUM
COATING
COOLANT LOOPS
CORROSION PROTECTION
DECONTAMINATION
DEPARTURE NUCLEATE BOILING
EFPH
FISSION PRODUCTS
FLUID FLOW
FUEL ELEMENTS
GRAPHITE
HEAT TRANSFER
HEATING
HIGH TEMPERATURE
IMPURITIES
INCONEL ALLOYS
IRON
IRRADIATION
METALLURGY
MTR
OPERATION
PLATING
POISONING
POROSITY
POWER
PROGRAMMING
PUMPS
PWR-1
RADIATION DOSES
RADIATION EFFECTS
REACTIVITY
REACTOR CORE
REACTOR MATERIALS
REACTOR TECHNOLOGY
SHUTDOWN
SOLUTIONS
SPECTRA
SPRAY
STAINLESS STEELS
STEELS
SWELLING
TESTING
THERMAL CONDUCTIVITY
THERMOCOUPLES
URANIUM 235
URANIUM DIOXIDE
ZIRCONIUM OXIDES