PRESSURIZED WATER REACTOR (PWR) PROJECT TECHNICAL PROGRESS REPORT FOR THE PERIOD AUGUST 24, 1958 TO OCTOBER 23, 1958
Technical Report
·
OSTI ID:4279121
An evaluation of the fission product activity levels during the 1000-hr full power run indicates the PWR core has one or more failed blanket rods. Rod drop uation made. A feasibility study has revealed that thermal and pressure cycling performed to date on core 1 does not limit the possibility of converting the reactor vessel test head to an operational head. Results obtained thus far on the PWR stress corrosion program indicate 1,150 deg F tempered 410 stainless steel is feasible for motor tubes. Test results to date on core 2 indicate that the 1 3/4-in.-diam. buffer piston will provide the deceleration necssary to limit impact velocity and control rod shafting stresses to acceptable values. Simulated water logging tests were conducted on wide fuel compartments. Fission gas release from compartmented-plate fuel elements was a factor of 1.5 to 2.0 hogher from compartments containing Al/sub 2/O/sub 3/-UO/sub 2/fuel than from compartments containing undiluted UO/sub 2/ Examination of Zircaloy tensile speciments of modified composition exposed in an in-pile hot water loop verified that addition of nickel increases hydrogen aborption. No dimensional changes were notedin copper diffusion bonded compartmented fuel plates after 1.6 at. % burnup. Oxide plate fuel ele ment samples of high compartment integrity have been successfully fabricated. A means of protecting Ag-15 In-5 Cd alternate control material alloy from corrosion attack in oxygenated water was developed. A twodimensional depletion study of core 1 was carried through 3000 EFPH of core life. An extensive series of one-rod-struck shutdown measurements was performed in the core 2 mock-up in order to determine the effects on shutdown of B/sup 10/ lumps. An experiment was performed in which the hydrogen density was reduced in the seedfuel region of the core 2 mock-up by the introduction of foamed plastic tape into the water channels in the seed. (For preceding period see WAPD-Mrp- 75.) (W.D.M.)
- Research Organization:
- Westinghouse Electric Corp. Bettis Plant, Pittsburgh
- DOE Contract Number:
- AT(11-1)-GEN-14
- NSA Number:
- NSA-13-005172
- OSTI ID:
- 4279121
- Report Number(s):
- WAPD-MRP-76
- Country of Publication:
- United States
- Language:
- English
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Technical Report
·
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·
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PRESSURIZED WATER REACTOR (PWR) PROJECT TECHNICAL PROGRESS REPORT FOR THE PERIOD JUNE 24, 1959 TO AUGUST 23, 1959
Technical Report
·
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·
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Related Subjects
ADSORPTION
ALUMINUM OXIDES
BLANKETS
BONDING
BORON 10
BURNUP
CADMIUM ALLOYS
CANNING
CONFIGURATION
CONTROL ELEMENTS
COOLANT LOOPS
COPPER
CORROSION
CORROSION PROTECTION
DEFORMATION
DENSITY
DIFFUSION
EXPANSION
FABRICATION
FAILURES
FERTILE MATERIALS
FISSION PRODUCTS
FISSIONABLE MATERIALS
FLUID FLOW
FOAMS
FUEL ELEMENTS
GASES
HEAT TRANSFER
HIGH TEMPERATURE
HYDROGEN
IMPACT SHOCK
IMPURITIES
IN PILE LOOPS
INDIUM ALLOYS
IRRADIATION
LEAKS
MATERIALS TESTING
MEASURED VALUES
MOCKUP
MODERATORS
MOTORS
NEUTRON FLUX
NICKEL
OXIDATION
OXIDES
PLATES
POLYMERS
POWER PLANTS
PRESSURE
PRESSURE VESSELS
PWR
RADIATION DOS
REACTORS
ALUMINUM OXIDES
BLANKETS
BONDING
BORON 10
BURNUP
CADMIUM ALLOYS
CANNING
CONFIGURATION
CONTROL ELEMENTS
COOLANT LOOPS
COPPER
CORROSION
CORROSION PROTECTION
DEFORMATION
DENSITY
DIFFUSION
EXPANSION
FABRICATION
FAILURES
FERTILE MATERIALS
FISSION PRODUCTS
FISSIONABLE MATERIALS
FLUID FLOW
FOAMS
FUEL ELEMENTS
GASES
HEAT TRANSFER
HIGH TEMPERATURE
HYDROGEN
IMPACT SHOCK
IMPURITIES
IN PILE LOOPS
INDIUM ALLOYS
IRRADIATION
LEAKS
MATERIALS TESTING
MEASURED VALUES
MOCKUP
MODERATORS
MOTORS
NEUTRON FLUX
NICKEL
OXIDATION
OXIDES
PLATES
POLYMERS
POWER PLANTS
PRESSURE
PRESSURE VESSELS
PWR
RADIATION DOS
REACTORS