Nuclear measurements for type 3 replacement cores for SM-1, SM-1A and PM-2A CE-3

Technical Report · Thu Jan 11 04:00:00 EST 1962

DOI:https://doi.org/10.2172/4812426· OSTI ID:4812426

Raby, T. M. ^[1]; Walthousen, L. D. ^[1]; Kemp, S. N. ^[1]; McCool, W. J. ^[1]; Sontheimer, K. C. ^[1]; Robinson, R. A. ^[1]

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

Description and results are given of an experimental program to evaluate the effect of utilizing Type 3 (SM-2) replacement cores in existing Army field plants SM-1, SM-1A, and PM-2A. SM-2 mockup fuel elements similar in composition to Type 3 fuel elements were employed to determine startup characteristics of Type 3 cores in SM-1, SM-1A, and PM-2A core configurations. Measurements include comprehensive power distribution, temperature coefficients, initial critical bank positions, control rod calibrations, critical rod configurations, and material coefficients, all obtained under cold and clean core conditions. The 45-element SM-1 and SM-1A configurations with SM-2 mockup fuel elements contain 36.4 kg U²³⁵ and an estimated 67.9 g B/sup 10/, while the 37-element PM-2A configuration with SM-2 mockup elements contains 30.0 kg U ²³⁵ and an estimated 56 g B¹⁰. (auth)

• Research Organization: Alco Products, Inc., Schenectady, NY (United States)
• Sponsoring Organization: USDOE
• NSA Number: NSA-16-009619
• OSTI ID: 4812426
• Report Number(s): APAE--100
• Country of Publication: United States
• Language: English

Related Subjects

BORON 10
BUCKLING
BURNUP
CONFIGURATION
CONTROL ELEMENTS
CRITICALITY
DISTRIBUTION
FAILURES
FUEL ELEMENTS
IMPURITIES
MASS
MEASURED VALUES
MOCKUP
MODERATORS
MULTIPLICATION FACTORS
NEUTRON FLUX
PM-2A
POISONING
POWER PLANTS
PRESSURE
PWR
REACTIVITY
REACTOR CORE
REACTOR TECHNOLOGY
RESONANCE ESCAPE PROBABILITY
RODS
SHUTDOWN
SM-1
SM-1A
SM-2
STANDARDS
STARTUP
TEMPERATURE
THERMAL NEUTRONS
THERMAL UTILIZATION
TRANSIENTS
URANIUM 235
WATER COOLANT