INTERIM REPORT ON THE USE OF SM-2 ELEMENTS IN SM-1, SM-1A AND PM-2A CORES

Technical Report · Tue Jun 20 00:00:00 EDT 1961

DOI:https://doi.org/10.2172/4026240· OSTI ID:4026240

Davidson, S L; Oggerino, J P

Interim results of analytical investigation of nuclear and thermal characteristics of SM-2 type fuel elements in SM-1, SM-lA, and PM-2Ae reactor cores are reported. Utilizing modified two-proup diffusion theory, predictions of power distribution and core and rod reactivity were performed. The calculations indicate that use of SM-2 fuel elemente in SM-1, SM-lA, and PM-2A is feasible from the nuclear standpoint. A steady state thermal analysis of each plant utilizing SM-2 elements was carried out. This analysis showed that the minimum departure from nuclear boiling ratios were considerably abovs the minimum value ftom the design criteria standpoint at both the operating and scram power levels. The investigation indicated that SM-2 elements can successfully be employed in SM-1, SM-lA, and PM-2A as replacement core elements. (auth)

• Research Organization: Alco Products, Inc., Schenectady, NY (United States)
• DOE Contract Number: AF(30-1)-2639
• NSA Number: NSA-15-024584
• OSTI ID: 4026240
• Report Number(s): APAE-Memo-291
• Resource Relation: Other Information: Orig. Receipt Date: 31-DEC-61
• Country of Publication: United States
• Language: English

Related Subjects

REACTOR TECHNOLOGY
CONTROL ELEMENTS
DIFFERENTIAL EQUATIONS
DIFFUSION
DISTRIBUTION
EQUATIONS
FUEL ELEMENTS
GROUP THEORY
NEUTRON FLUX
NUCLEATE BOILING
OPERATION
PM-2A
POWER PLANTS
PRESSURE
REACTIVITY
REACTOR CORE
REACTORS
SHUTDOWN
SM-1
SM-2
THERMODYNAMICS
WATER COOLANT
WATER MODERATOR