PRESSURIZED WATER REACTOR (PWR) PROJECT. Technical Progress Report, August 24, 1961-October 23, 1961

Technical Report · Wed Oct 31 04:00:00 EST 1962

OSTI ID:4813179

The thermal performance of the PWR-2 was re-evaluated based on the latest nuclear and thernmal information, design changes, and the use of the XlTE code. The seed cluster design was re-examined both analytically and experimentally from the standpoint of fuel plate stability, and a revised design was submitted for approval. Preliminary depletion studies established a Seed 2 fuel loading necessary to achieve 20,000 EFPH. The most highly depleted rod from the PWTR-1 blanket was examined after two seed lives exposure. The initial approach to criticality on PWR-1 Seed 3 was suecessfully conducted on October 7, 1961. Analysis of fission gas release from swelled compartments of 25 ZrO/sub 2/ + UO/sub 2/ fuel plates showed that the gas release increases with increasing burnup and/or time inpile. A calculation was performed of the thermal spectrum in the PWR-2 seIf-shielded boron by means of a muitigroup thermal Monte Carlo program, MARC. A measurement was made of a PWT-2 mock-up containing poison elements which meet the PWR-2 design specifications. The concept of the Safety Injection System was modified to utilize the pressurizer relief valves to reduce primary plant pressure during a loss of coolant accident involving small breaksThe a-c type static inverter development unit was approved as the reference design for the PWR-2 rod control system. Preliminary radiochemical data obtained at initial criticality for Seed 3 indicated that the new seed does not contain excessive uranium surface contamination. (M.C.G.)

• Research Organization: Westinghouse Electric Corp. Bettis Atomic Power Lab., Pittsburgh
• DOE Contract Number: AT(11-1)-GEN-14
• NSA Number: NSA-16-006223
• OSTI ID: 4813179
• Report Number(s): WAPD-MRP-94
• Country of Publication: United States
• Language: English

Related Subjects

ACCIDENTS
BLANKETS
BORON
BURNUP
CANNING
CONFIGURATION
CONTAMINATION
CONTROL ELEMENTS
CONTROL SYSTEMS
COOLANT LOOPS
COOLANTS
CRACKS
CRITICALITY
DEFORMATION
FAILURES
FISSION PRODUCTS
FUEL CANS
FUEL ELEMENTS
GASES
GROUP THEORY
HEAT TRANSFER
HIGH TEMPERATURE
IMPURITIES
INJECTION
IRRADIATION
LEAKS
LOSSES
MATERIALS TESTING
MEASURED VALUES
MECHANICAL PROPERTIES
MOCKUP
MONTE CARLO METHOD
NEUTRON FLUX
PLANNING
PLATES
POISONING
POWER PLANTS
PRESSURE
PROGRAMMING
PWR
QUALITATIVE ANALYSIS
RADIATION EFFECTS
RADIOCHEMISTRY
REACTOR CORE
REACTOR SAFETY
REACTOR TECHNOLOGY
REACTORS
RODS
SHUTDOWN
SPECTRA
STABILITY
STARTUP
SURFACES