CVTR PROJECT. CAROLINAS VIRGINIA NUCLEAR POWER ASSOCIATES, INC., MONTHLY PROGRESS REPORT, JANUARY 1961
The A-2 and A-4 capsules for the irradiation program were completed in preparation for insertion in WTR during February. The M-1 and M-3 capsules remain under irradiation. The In-Pile Loop has now accumulated about 50 equivalent full-power days of exposure, or 25% of the desired full-power exposure. Fabrication of the rem ten pieces of integral finned tubing (cladding) for CVTR was completed. No major processing problems were encoun tered. The tubing will be shipped to WAPD for inspection during February. Some difficulties were experienced in welding Phase II fuel-rod end closures. Shrinkage defects were detected, apparently caused by an unbalanced weld bead cooling rate between the closure end plug and the fuel tubing. Further test welds are being made in order to improve techniques for the single pass weld. Experiences on repairing defective welds have resuited in 90% reclamation. Work continued on CVTR first- core burn-up and powerdistribution calculatiore. CANDLE results indicate prior estimates of first-core U-235 content will have to be increased. Fabrication of all the CVTR Phase II components and hardware was completed. The pressure-tube assembly was installed in Loop D and testing was started. Debugging of the impulsive-burst testing machine indicated a need for minor modifications. Trial runs were made with a stainless-steel specimen. A jumper connector and pont (Conoseal) test fitting was subjected to 149 thermal cycles at 100 to 520 deg F at 1800 psig. Maximum leak rate was less than 1 lb/year. A layout of the four- baffle concept was completed and detailing started. A vacuum drying test was conducted using the Phase I pressure tube containing ons fuel assembly. The pressure tube was completely dried of approximately 39 liters of water in 15 hr. All the components required for the coretruction of the control-rod drive assembly were completed. Assembly of the components is nearing completion. The critical experiments were continued with the measurement of the temperature coefficient. The net reactivity change between 22 and 840"C was measured as - 1.5% DELTA k. Measurements of the coolant void coefficient were made at the critical facility for various purities of heavy water. With D/sub 2/O of approximately 90% purity, the ccefficient was found to be +1 x 10-4 DELTA k per tube. With D/sub 2/O of approximately 95% purity, the ccefficient was only slightly positive, +2 x 10/sup -5/ DELTA k per tube. As a result the heavy water coolant in the CVTR will be maintained above a specified purity, which remaire to be determined. (For preceding period see WCAP-4002.) (auth)
- Research Organization:
- Originating Research Org. not identified
- NSA Number:
- NSA-15-014003
- OSTI ID:
- 4054424
- Report Number(s):
- WCAP-4051
- Country of Publication:
- United States
- Language:
- English
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