ML-1-1A Core studies with the GCRE critical assembly

Technical Report · Fri Nov 27 04:00:00 EST 1959

DOI:https://doi.org/10.2172/4206668· OSTI ID:4206668

Egen, R. A.; Hogan, W. S.; Dingee, D. A.; Chastain, J. W.

Critical assembly studies were conducted tc provide physics and engineering data to aid in developing the Mobile Low-Power Reactor (ML-1). The ML-1-lA core was critical with 59 elements containing 17,906.71 g of U²³⁵ and had an excess reactivity of 0.381 x 10^-2 DELTA k/k at a moderator temperature of 24.91 deg C. The ratio of maximum element power to core-averaged power was approximately 1.09. The ratio of maximum to core-averaged thermal flux was approximately 1.10. At an 18-deg separation, the shutdown worth of the cadmium-covered control-blade mock-up was 1.14 x 10^-2 DELTA k/k for a 69 element core. Radial and upper axial reflector-moderator void coefficients were - 0.59 plus or minus 0.07 and -0.36S plus or minus 0.015 x 10^-2 DELTA k/ k.per in., respectively. Two lA production fuel elements were evaluated in the critical assembly core. The results predict that the production elements tested contained roughly the same fuel as the critical assembly element and an additional 772 g of stainless steel equivalent on the average. Radial power and neutron flux distributions were measured in a 19-pin lB fuel element. Fairly uniform distributions were observed. Data to evaluate the thermal utilization of this element were obtained.

• Research Organization: Battelle Memorial Inst., Columbus, Ohio
• DOE Contract Number: W-7405-ENG-92
• NSA Number: NSA-14-006031
• OSTI ID: 4206668
• Report Number(s): BMI-1396
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
42 ENGINEERING
CADMIUM
CONTROL ELEMENTS
CRITICAL ASSEMBLIES
DISTRIBUTION
FUEL ELEMENTS
ML-1
MOCKUP
MODERATORS
NEUTRON FLUX
POWER
POWER PLANTS
REACTIVITY
REACTOR CORE
REACTORS
REFLECTORS
SHUTDOWN
STAINLESS STEELS
TEMPERATURE
THERMAL NEUTRONS
THERMAL UTILIZATION
URANIUM 235
ZONES