SM-2 REACTOR CORE AND VESSEL REVIEW REPORT FOR AUGUST 25, 1959 TO DECEMBER 14, 1959

Technical Report · Thu Dec 24 00:00:00 EST 1959

DOI:https://doi.org/10.2172/4173687· OSTI ID:4173687

The most adverse power distribution was revised based on a comparison of PDQ calculations and measurements made during the SM-2 flexible experiments. A review of the basic nuclear data and calculational models employed in the SM-2 nuclear analysis was rnade. A comparison between initial reactivily, hot-to-cold reactivity change, and xenon reactivity with experiment was rnade. Based on a revised power distribution, the core flow requirement was reestimated to be 7800 gpm. Tentative designs of the core support and fuel element structure were prepared and evaluated for pressure drop and flow distribu-tion. The ETR and MTR irradiation programs are suramarized. The TIG process for welding elements is discussed. Specimens of Eu/sub 2/O/sub 3/ dispersions in stainless steel were autoclave tested. Static deflection messurements indicated that a fuel element with cold rolled plates will have a deflection aproximately 18% lower than annealed plates. measurement of plate collapse on two elements indicated possible collapse in the range 140 to 164% of rated flow. Flow distribution and pressure drop tests were made for several core support structure configurations. Mockup experiments on the SM-2 initial cold, clean and SM-2 mid-life cores were completed. Limited power distribution and flux distributions were performed in the clean mockup. The hot-to-cold reactivily change was measured by aluminum displacement as 90. The average B/sup 10/ and U/sup 235/ worth in the clean mockup was measured as 43 and 0.157 cents /g. The reactivity effect of replacing control rod fuel assemblies by stationary fuel elements was measured in the clean mochup. Stuck rod positions were measured in the mid-life mockup. (For preceding period see APAE-memo-223.) (W.D.W.)

• Research Organization: Alco Products, Inc., Schenectady, NY (United States)
• DOE Contract Number: AT(30-3)-326
• NSA Number: NSA-14-013467
• OSTI ID: 4173687
• Report Number(s): APAE-Memo-235
• Resource Relation: Other Information: Orig. Receipt Date: 31-DEC-60
• Country of Publication: United States
• Language: English

Related Subjects

REACTOR TECHNOLOGY
ANNEALING
BURNUP
CONFIGURATION
CONTROL ELEMENTS
DEFORMATION
DISPERSIONS
DISTRIBUTION
EQUATIONS
EUROPIUM OXIDES
FUEL ELEMENTS
HEAT TREATMENTS
IRRADIATION
LIQUID FLOW
MEASURED VALUES
MECHANICAL STRUCTURES
MOCKUP
NEUTRON FLUX
NUCLEAR REACTIONS
POISONING
POWER PLANTS
PRESSURE
PROGRAMMING
REACTIVITY
REACTOR CORE
REACTORS
ROLLING
SM-2
STAINLESS STEELS
TESTING
VARIATIONS
WATER COOLANT
WELDING
XENON