FUEL CYCLE PROGRAM. A BOILING WATER REACTOR RESEARCH AND DEVELOPMENT PROGRAM. Quarterly Progress Report No. 12, April-June 1963

Technical Report · Mon Jul 01 04:00:00 EDT 1963

OSTI ID:4624997

Howard, C.L. comp.

Fuel irradiatioas in the VBWR have resulted in exposure increases of 1200 to 1500 Mwd/t for the lead assemblies of each type. Preliminary tests in the hydraulic stability loop using sinusoidal oscillation of power input show that each test condition has more than one resonance frequency and that the resonance frequency is dependent on the test condition. A revised noise analysis code named DART was used to obtain the reactivity noise spectrums for natural circulation operation of VBWR. Burnout tests with an axial heat flux variation in both a cosine and truncated cosine distribution show that the results can be predicted to plus or minus 10% by calculations based on uniform heat flux data. The calculation involves determination of local quality and heat flux along the test heater and comparison of these values to the previously determined correlation of burnout heat flux with local conditions. Thus, it is shown that burnout depends primarily on the local heat flux, quality, amd flow conditions, and not the shape of the flux distribution. Data for pressure drop in a test section having a rough liner to increase the critical heat flux show that the values are reasonable to consider for reactor application. All previous results from the heat transfer task are summarized. (N.W.R.)

• Research Organization: General Electric Co. Atomic Power Equipment Dept., San Jose, Calif.
• NSA Number: NSA-17-040271
• OSTI ID: 4624997
• Report Number(s): GEAP-4301
• Country of Publication: United States
• Language: English

Related Subjects

BACKGROUND
BOILING
BURNUP
COOLANT LOOPS
FLUID FLOW
FUEL CYCLE
FUEL ELEMENTS
HEAT TRANSFER
HYDRAULICS
IRRADIATION
LEAD
NEUTRON FLUX
OSCILLATIONS
PRESSURE
PROGRAMMING
REACTIVITY
REACTOR TECHNOLOGY
REACTORS
RESONANCE
STABILITY
TESTING
VBWR
WATER COOLANT
WATER MODERATOR