YANKEE CORE EVALUATION PROGRAM. Quarterly Progress Report for the Period Ending March 31, 1963

Technical Report · Fri Apr 26 04:00:00 EST 1963

OSTI ID:4700392

The initiation of shipping and examination activities on irradiated fuel elements, and the completion of design and testing efforts on all related hardware'' items are described. Details on the planning and preparation activities which preceded to initiation of core examination work are provided. Efforts relating to the examination of Yankee fuel assemblies and control rods, including the arrangements and equipment for transporting the core components to the post-irradiation facility, the design and procurement of special equipment required for the examination work, and performance of the actual data-gathering and related activities are discussed. Transportation of three Yankee irradiated fuel assemblies and one control rod absorber from the Yankee Site to the Westinghouse Post-Irradiation Facility is described. Initial efforts on the underwater examination and disassembly operations on irradiated fuel elements were completed. Results of the gamma scans made on three irradiated Yankee fuel assemblies are presented. The evaluation of the data and to its significance with regards to the performance of Yankee Core I is described. Procedures to be followed in the core examination aspects of the project are defined. Initial evaluations were made of the data obtained. Calculations of predicted burnups were made for samples to be analyzed and evaluated under this project. Initial evaluations were carried out on the effect of the spatial variation of neutron spectrum in Yankee Core I. Gamma scanning measurements performed on three irradiated Yankee fuel assemblies were evaluated. The revision of nuclear design methods, taking into account information obtained in tests, is described. The initial efforts made on the adaptation of fuel depletion computer programs to the needs of this project are discussed. Studies made on methods of evaluating resonance capture rates are described. Exploratory calculations for multigroup neutron spectrum analysis are given. Methods for calculating thermal utilization were evaluated. (auth)

• Research Organization: Westinghouse Electric Corp. Atomic Power Div., Pittsburgh
• NSA Number: NSA-17-026872
• OSTI ID: 4700392
• Report Number(s): WCAP-6054
• Country of Publication: United States
• Language: English

Related Subjects

BURNUP
COMPUTERS
CONTROL ELEMENTS
FUEL ELEMENTS
GAMMA RADIATION
GROUP THEORY
IRRADIATION
NEUTRONS
PERFORMANCE
PLANNING
POWER PLANTS
PROGRAMMING
REACTOR CORE
REACTOR TECHNOLOGY
REACTORS
RECORDING SYSTEMS
REMOTE HANDLING
RESONANCE ESCAPE PROBABILITY
SERVOMECHANISMS
SPECTRA
STANDARDS
TESTING
THERMAL UTILIZATION
TRANSPORT
VARIATIONS
WATER
YAEC