Extended SM-2 Critical Experiments: CE-2

Technical Report · Fri Jun 30 04:00:00 EDT 1961

DOI:https://doi.org/10.2172/4818284· OSTI ID:4818284

McCool, W. J. ^[1]; Robinson, R. A. ^[1]; Weiss, S. H. ^[1]; Raby, T. M. ^[1]; Schrader, E. W. ^[1]; Walthousen, L. D. ^[1]

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1. Alco Products, Inc., Schenectady, NY (United States)

A description and results of a second series of critical experiments performed on the SM-2 core mockup are presented. The SM-2 core mockup contains 36.4 kg of U-235 and an estimated 67.9 gm B-10. The equivalent diameter and the active height are about 22 in.; the metal-to-water volume ratio is 0.344. Data are presented on activation, reactivity, and stuck rod measurements. All measurements were conducted on the open 7 control rod array employing 38 stationary fuel elements. Activation measurements consisted of neutron flux measurements using uranium fission foils for relative power distribution studies, the effect of flux suppressors on reducing power peaks, blocked coolant channel measurements, and gamma dose distribution. Reactivity measurements were performed to determine the effect of flow divider, flux suppressors, and simulated high temperature and pressure operation, B-10 loading in the SM-2 core, and core material coefficients. For the latter, the worth in cents per gram or cents per cm3 was determined at a simulated temperature of 510°F for B-10, U-235, stainless steel, and void. Stuck rod measurements were made to obtain an indication of the criticality margin in the event one or more control rods should stick in the operating position.

• Research Organization: Alco Products, Inc., Schenectady, NY (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Atomic Energy Commission (AEC)
• NSA Number: NSA-16-002398
• OSTI ID: 4818284
• Report Number(s): APAE-54(Suppl.1)
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BORON
CONFIGURATION
CONTROL ELEMENTS
CRITICALITY
Core Mockup
Criticality
DISTRIBUTION
FOILS
FUEL CANS
Flux Suppressors
Fuel Elements
MEASURED VALUES
MOCKUP
NEUTRON FLUX
Nuclear Criticality Safety Program (NCSP)
PRESSURE
REACTIVITY
Reactivity Measurements
STAINLESS STEELS
TEMPERATURE
URANIUM 235