PRESSURIZED WATER REACTOR (PWR) PROJECT TECHNICAL PROGRESS REPORT FOR THE PERIOD DECEMBER 24, 1957 TO FEBRUARY 23, 1958

Technical Report · Fri Oct 31 04:00:00 EST 1958

OSTI ID:4305917

The results of corrosion testing of Auric Brazes (24 K gold, 80-20 gold- copper, 50-50 gold-copper) indicate that from a corrosion standpoint there is little or no difference among the three alloys. A computer program was established for determining subassembly pressure and thermal stresses in Seed 2. Preliminary data from all of the in stalled seed metal thermocouples proved unreliable. Nuclear peaking factors were evaluated for the beginning of Seed 2 life (hot clean) for various conditions of loading. Satisfactory performance tests demonstrating the adequacy of the reactor vessel closure seal weld cutting machine for the vessel to seal cut were performed. Preliminary results of the nuclear analysis of the 20 control rod core under study for Core 2 indlcated that the proposed design would yield an unfavorable seed-blanket power sharing. Air flow studies in a quarter-scale model of the pressure vessel and simulated internal components were completed. Effort on fuel element design was concertrated on determining the factors which will lead to the selection of the most desirable ceramic fuel for the Core 2 blanket from the standpoint of penformance capability, mechanieal stability, and cost. Progress has been made in the development of a nondestructive method of U/sup 235/ assay of fuel fillers. Fission gas release measurements on samples of UO/sub 2.10/ showed no acceleration of fission gas release as compared to the release from UO/sub 2.0/ Examination of the failed WAPD 29-10 sample indicated profuse hydride formations in the Zircaloy-2. Analyses indicated the presence of 4000 ppm of hydrogen in these regions. No gross hydride pickup or irradiation induced embrittlement were discerned in the Zircaloy of the WAPD 30-3 fuel elements. PWR Core 2 fuel element samples were fabricated vdth 100% integrity using an improved fabrication process. Modifications in the reference Ag--In control rod alloy resulted in marked improvements in streapth propenties. The estimated activation energy for Kr/sup 85/ diffusion in high density UO/sub 2/ is 61.2 kcal/mole. Seed 2 reactivity lifetime studies were completed for twoo proposed seed loadings. Based on a reactivity lifetime of 6000 EFPH for Core 1, Seed 1, the reactivity lifetime of a 90 kg Seed 2 with 150 grams of natural boron is predicted to be approximately 7400 EFPH. (For preceding period see WAPD-MRP-71.) (D.E.B.)

• Research Organization: Westinghouse Electric Corp. Bettis Plant, Pittsburgh
• DOE Contract Number: AT(11-1)-GEN-14
• NSA Number: NSA-12-007482
• OSTI ID: 4305917
• Report Number(s): WAPD-MRP-72
• Country of Publication: United States
• Language: English

Related Subjects

ADSORPTION-- BRITTLENESS-- FUEL ELEMENTS-- HYDRIDES-- IRRADIATION-- POWER PLANTS-- PRESSURE-- PWR-- REACTORS-- WATER COOLANT-- WATER MODERATOR-- ZIRCALOY
AIR-- GAS FLOW-- MOCKUP-- POWER PLANTS-- PRESSURE-- PRESSURE VESSELS-- PWR-- REACTORS-- WATER COOLANT-- WATER MODERATOR
BLANKETS-- CERAMICS-- ECONOMICS-- FUEL ELEMENTS-- FUELS-- MECHANICAL PROPERTIES-- PERFORMANCE-- PLANNING-- POWER PLANTS-- PRESSURE-- PWR-- QUANTITATIVE ANALYSIS-- REACTORS-- STABILITY-- WATER COOLANT-- WATER MODERATOR
BLANKETS-- CONTROL ELEMENTS-- PLANNING-- POWER-- POWER PLANTS-- PRESSURE-- PWR-- REACTOR CORE-- REACTORS-- RODS- - WATER COOLANT-- WATER MODERATOR
BURNUP-
PHYSICS