Summary of K Reactor outlet temperature limits

Technical Report · Mon May 13 04:00:00 EDT 1957

DOI:https://doi.org/10.2172/10174960· OSTI ID:10174960

Hall, R E

The purpose of this report is to summarize all actual and potential power level limits under which the K Reactors may be forced to operate during the next year. In addition, a summary of the methods being followed to eliminate each is to be discussed along with a graphical presentation of the relationship of the various limits. For the purpose of this report, it was assumed that all power levels will be attainable from a physics aspect since these problems are discussed elsewhere. It is not the intent of this report to recommend that these power levels be attained but only to indicate what production levels are possible through operation on any one limit. Seven outlet temperature limits govern operation at the K Reactors. They are: TBI Limit; Crosstie Limit; Rear Header Saturation Limit; Bulk Outlet Temperature Limit; Tube Corrosion Limit; Temperature Monitor Limit; and Rupture Control Point. Operation during the summer months of 1957 will require cuts in power in order to remain within these limits unless modes of circumventing a few are found. The limits are shown graphically in the appendix at the various flow rates probable. From these curves it is evident that the Low Trip TBI Limit, the ``Crosstie`` Limit, and the ``90 Bulk`` must be relaxed in order to continue the stepwise approach to a Rupture Control Point. Current plans call for a flow increase to 155,000 gpm on about June 1, 1957, in order to operate at 1225 KW/tube. On July 1, 1957, plans call for increasing flow to 167,000 gpm and raising tube powers to 1300 KW/tube, until about November 1 when flow will again be reduced to 155,000 gpm without reducing level.

• Research Organization: General Electric Co., Richland, WA (United States). Hanford Atomic Products Operation
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 10174960
• Report Number(s): HW--50183; ON: DE94016992
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220600
CORROSION
FLOW RATE
HANFORD PRODUCTION REACTORS
HEAT TRANSFER
HYDRAULICS
LIMITING VALUES
REACTOR COOLING SYSTEMS
REACTOR OPERATION
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS
TEMPERATURE MEASUREMENT