ERDL-NPFOR QUARTERLY PROGRESS REPORT NO. 7 FOR JANUARY THROUGH MARCH 1959

Technical Report · Wed Apr 01 00:00:00 EST 1959

OSTI ID:4242943

Corrosion testing of heat exchanger test units is described. In the nucleate boiling program Martin Hardcoat aluminum appeared to provide satisfactory electrical insulation for the test section, the sensitivity of the void detection equipment was improved so that a 1% void can be successfully measured, and a redesign of the test sections was initiated to obtain closer correspondence between the section and an actual fuel element. In the critical experiment program zero power check point experiments the critical water height with three plastic spacers between fuel bundles was determined to be 11.05-in. above the bottom of the active core, gross and fine flux measurements were completed, the reactivity of ERDL, APPR, and ORNL fuel elements were compared, the worth of a Martin APPR prototype control rod was compared with two APPR control rods supplied by ERDL, and the results of analytical studies of the core generally compared well with experimental results. In the critical experiment program core extrapolation experiments fabrication of 115 follower box fuel plates was completed, a modified safety rod actuator was tested and found to meet specifications, analytical predictions of experimental results for all nine cores were completed, and the design of the complete experimental program was completed. (For preceding period scc MND-E-2004.) (W.D.M.)

• Research Organization: Martin Co. Nuclear Div., Baltimore
• DOE Contract Number: DA-44-009-ENG-3318
• NSA Number: NSA-13-015772
• OSTI ID: 4242943
• Report Number(s): MND-E-2005
• Resource Relation: Other Information: Orig. Receipt Date: 31-DEC-59
• Country of Publication: United States
• Language: English

Related Subjects

REACTORS
ALUMINUM- COATING- ELECTRIC CONDUCTIVITY- FUEL ELEMENTS- MATERIALS TESTING- MEASURED VALUES- NUCLEATE BOILING- PLANNING- POROSITY- POWER PLANTS- REACTORS- SENSITIVITY- SM-1- ZONES
CONFIGURATION- CONTROL ELEMENTS- CRITICALITY- FABRICATION- FUEL ELEMENTS- MEASURED VALUES- NEUTRON FLUX- ORNL- PLATES- POLYMERS- POWER- POWER PLANTS- REACTIVITY- REACTORS- RODS- SM-1- SPACERS- VOLUME- WATER
CORROSION- HEAT EXCHANGERS- POWER PLANTS- REACTORS- SM-1- TESTING