REACTOR ANALYSIS FOR THE ARMY PACKAGE POWER REACTOR NO. 1

Technical Report · Tue May 29 04:00:00 EDT 1956

OSTI ID:4301685

Gallagher, J.G. ed.

The reactor analysis of the critical experiment and thc APPR-I resulted in a loading of the APPR-1 of 2I.098 gm of B-I0 with 22.5 kg U-235. This loading will rcsult ln adequate reactlvity for a core life of I3 MWYR bascd on uniform burnup of U-235 and B-10. Calculations iindicate that five of the seven control rods provided are more than adequate to shut the reactor down at any time. The temperature coefficient of reactivity should be at least -2 x 10/sup -4/ DELTA K/ deg F. (auth)

• Research Organization: Alco Products, Inc., Schenectady, N.Y.
• NSA Number: NSA-13-000954
• OSTI ID: 4301685
• Report Number(s): APAE-7
• Country of Publication: United States
• Language: English

Related Subjects

APPR-1
BORON 10
BURNUP
CONFIGURATION
CONTROL ELEMENTS
CRITICALITY
EQUATIONS
MASS
MEASURED VALUES
NEUTRON FLUX
POISONING
POWER PLANTS
REACTIVITY
REACTOR CORE
REACTOR FUELING
REACTOR SAFETY
REACTORS
RODS
SHUTDOWN
STABILITY
TEMPERATURE
TRANSIENTS
URANIUM 235