ERDL-NPFO--QUARTERLY PROGRESS REPORT NO. 6 FOR OCTOBER THROUGH DECEMBER 1958

Technical Report · Sat Oct 31 00:00:00 EST 1959

OSTI ID:4274417

Autoclave tests of type 430 stalnless steel were conducted. Corroslon testing of heat exchangers is discussed. ln the nucleate boiling program recorded outputs of 1/2 and 1 inch were observed with the void detector for 3 and 5% voids, respectively. A transient test at the SPERT facility with the APPR ZPE core resulted in a peak power of 110 Mw on a period of 5 msec, for a total energy release under the burst of 16.5 Mwsec. Maximum fuel plate surface temperature was 487 deg C, and some buckllng and blistering were observed. Critical experiments on the 45-element core are described. In the core extrapolation experiments an excursion analysis was completed for the most reactive of the nine cores. (For preceding period see MND-E- 2003.) (W.D.M.)

• Research Organization: Martin Co. Nuclear Div., Baltimore
• DOE Contract Number: DA-44-009-ENG-3318
• NSA Number: NSA-13-008283
• OSTI ID: 4274417
• Report Number(s): MND-E-2004
• Resource Relation: Other Information: Orig. Receipt Date: 31-DEC-59
• Country of Publication: United States
• Language: English

Related Subjects

REACTORS
APPR-S
BURNOUT
CONFIGURATION
CORROSION
CORROSION PROTECTION
CRITICALITY
DEFORMATION
DIFFUSION
EFFICIENCY
EXCURSIONS
FUEL ELEMENTS
FUEL PLATES
HEAT EXCHANGERS
HIGH TEMPERATURE
IRRADIATION
MASS
MATERIALS TESTING
MEASURED VALUES
MODERATORS
NEUTRON FLUX
NEUTRONS
NUCLEATE BOILING
POWER PLANTS
PROMPT NEUTRONS
REACTIVITY
REACTOR CORE
REACTOR FUELING
SHUTDOWN
SPERT-1
STAINLESS STEELS
SURFACES
TEMPERATURE
THERMAL STRESSES
TRANSIENTS
VOID COEFFICIENT
ZONES