PRESSURIZED WATER REACTOR (PWR) PROJECT TECHNICAL PROGRESS REPORT FOR THE PERIOD APRIL 24, 1959 TO JUNE 23, 1959

Technical Report · Sat Oct 31 04:00:00 EST 1959

OSTI ID:4215953

The average rates of escape of soluble ionic fission products into the PWR primary coolant continued to increase. The alkaline permanganate --ammonium citrate decontamination process gave a very good decontamination factor when applled to contaminated 304 SS boiler tube specimens in a small laboratory flow loop. Thermal analysis of PWR-1 performance utilizing new nuclear design information for 5000 and 5500 EFPH was completed. The activity levels of the control rod shrouds, the tie rods, and the blanket exit water instrumentation assemblies were computed for up to 6 months after the end of Seed 1 life. The mechanical design effort on PWR-2 was largely devoted to the evaluation of the effects of the various core lengths on the design of individual core components. A study of the shroud design problems assoclated with control rod extensions and the methods of refueling cores of various lengths was completed. A new method of mounting thermocouple guide tubes in the upper shroud was devised. Studies indicated that holding the core in the vessel by clamping the support flange between the flanges of the reactor vessel and head is feasible. Failure of a PWR- 1 type rod in the X-1-n test confirmed the hydriding susceptibility of zircaloy-2 in this configuration as well as the advisability of removing Ni from the alloy. Thermal conductivity tests of U0/sub 2/ rods in-pile indicated that the effective thermal conductivities increase by a factor of more than two when the diametrical gap is reduced from 3.5 to 1.5 mils. Modifications in pressure bonding techniques for oxide plate fabrication significantly improved quality. Results of exposure tests to 650 deg F water, pH 9-10.5, with LiOH, 2200 psi, showed that BeO -- UO/sub 2/, ZrO/sub 2/--CaO -- U0/sub 2/, and ZrO/sub 2/-- U0/ sub 2/ ceramic fuels are stable. A three-dimensional depletion study of PWR-1 was carried through Seed 1 life and is now complete through 3000 EFPH of Seed 2 life. Threedimensional synthesis studies of Xe transient behavior observed at Shippingport predicted control rod worths in good agreement with measured values. Two analytical methods used to calculate the ratio of neutron activation in self- shielded boron lumps in adjacent fuel material were evaluated. Measurements on the PWR-2 mockup indicated that the use of control rod extensions increases the one-rod-stuck shutdown margin by --0.4% DELTA k/k for a 112 kg U/sup 235/ loading. Epithermal and thermal neutron activation measurements were performed in and near boron lumps in a five-cluster slab assembly a examine the self- shielding factors at various energies. ( For preceding period see WAPD-MRP79.) ( W.D.M.)

• Research Organization: Westinghouse Electric Corp. Bettis Plant, Pittsburgh
• DOE Contract Number: AT(11-1)-GEN-14
• NSA Number: NSA-13-018741
• OSTI ID: 4215953
• Report Number(s): WAPD-MRP-80
• Country of Publication: United States
• Language: English

Related Subjects

ACIDITY-- CERAMICS-- HIGH TEMPERATURE-- LITHIUM HYDROXIDES-- POWER PLANTS-- PRESSURE-- PWR-- REACTORS-- STABILITY-- WATER
ACTIVATION-- BORON-- EPITHERMAL NEUTRONS-- MEASURED VALUES-- POWER PLANTS-- PRESSURE-- PWR-- REACTORS-- SHIELDING-- THERMAL NEUTRONS-- WATER
AMMONIUM COMPOUNDS-- CITRIC ACID-- DECONTAMINATION-- PERMANGANATES-- POWER PLANTS-- PRESSURE-- PWR-- REACTORS-- WATER
BLANKETS-- CONTROL ELEMENTS-- MACHINE PARTS-- POWER PLANTS-- PRESSURE-- PWR-- RADIOACTIVITY-- REACTORS-- RODS-- WATER
BONDING-- FABRICATION-- OXIDES-- PLATES-- POWER PLANTS-- PRESSURE-- PWR-- REACTORS-- WATER
CALCIUM OXIDES-- CERAMICS-- FUEL ELEMENTS-- POWER PLANT
REACTORS