Startup and Initial Testing of SM-1 Core II with Special Components

Technical Report · Wed Feb 28 04:00:00 EST 1962

DOI:https://doi.org/10.2172/4785533· OSTI ID:4785533

Moote, F. G. ^[1]; Schrader, E. W. ^[1]

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

The loading operation for SM-1 Core II is described. Results of startup physics measurements (Test A-300 Series) and fission product iodine monitoring in the primary coolant are given. The SM-1 Core II initial loading progressed satisfactorily, fulfilling the predictions of the zero power experiment performed at the Alco Criticality Facility. The initial cold clean five rod bank position was 6.53 in.; the initial hot, no xenon, five rod bank position was 9.62 in.; the initial hot, equilibrium xenon, five rod bank position was 11.41 in.; and the initial hot, peak xenon, five rod bank position was 12.14 in. Rods A and B were 19.00 in. in all four measurements. Stuck rod measurements indicated that an adequate shutdown margin was available with 20% of the rods fully withdrawn. All rod calibrations indicated a distinct shift and broadening of the peaks when compared with similar Core I calibrations. The temperature coefficient for Core II was -3.5 cents/°F at 440°F. Equilibrium xenon was worth approximately $$\$$$$3.00 while peak xenon was worth - $$\$$$$4.43, both relative to the hot, no xenon core condition. During the period June 2, 1961 through September 30, 1961, the reactor operated at a total of 935.68°F days which is equivalent to 1.34 MWYR of energy release and represents an average load factor of 44% typical of training periods. The estimated reactivity in the core at startup is $$\$$$$10.00. A core life of 12.2 MWYR is predicted for the original configuration of Core II. The results of gross fission product iodine monitoring showed that those levels were about one-third to one-half of those found at the end of Core I Operation.

• 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-16-014277
• OSTI ID: 4785533
• Report Number(s): APAE-Memo-305
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BURNUP
CONFIGURATION
CONTAMINATION
CONTROL ELEMENTS
COOLANT LOOPS
COOLANTS
CRITICAL ASSEMBLIES
CRITICALITY
Equilibrium Xenon
FAILURES
FISSION PRODUCTS
FUEL ELEMENTS
Fission Product
HIGH TEMPERATURE
IODINE
LOW TEMPERATURE
MASS
MEASURED VALUES
MONITORING
MOTION
MULTIPLICATION FACTORS
NEUTRON FLUX
NUMERICALS
Nuclear Criticality Safety Program (NCSP)
OPERATION
POISONING
POWER PLANTS
PRESSURE
RADIATION DOSES
REACTIVITY
REACTOR CORE
REACTOR FUELING
REACTOR SAFETY
REMOTE CONTROL
REMOTE HANDLING
RODS
Rod Bank Position
SERVOMECHANISMS
SHUTDOWN
SM-1
STABILITY
STANDARDS
STARTUP
TEMPERATURE
TESTING
Temperature Coefficient
VARIATIONS
WATER COOLANT
XENON