SDR PROJECT QUARTERLY TECHNICAL PROGRESS REPORT FOR THE PERIOD MAY 1, 1957 THROUGH JULY 31, 1957

Technical Report · Mon Sep 30 04:00:00 EDT 1957

DOI:https://doi.org/10.2172/4318564· OSTI ID:4318564

Engineering studies were made and experimental work was carried out with the objective or demonstrating the feasibility of separation of Na and D/sub 2/O in the SDR reactor. For the engineering studies, a through-tube reactor design was selected. Layouts of fuel-coolant tube and header arrangements were made with a view towards minimizing the probability of mechanical failures of these sodium system components. Preliminary studies on Na and D/sub 2/O system requirements and on the design of the D/sub 2/O moderator tank or calandria were started. A survey was made of possible barrier materials, i.e., materials which may be located between the fuel-coolant tubes and the calandria tubes to minimize the consequences of single or multipletube failures. Mechanical arrangements for mounting and supporting barrier materials and for detecting leaks were investigated. Conceptual designs of equipment for testing the mechanical integrity of fuel-coolant tube and header joints were completed. Major components of a singlefailure rig, in which barrier materials can be subjected to Na streams that simulate Na system failures, were designed, constructed, and assembled. Preliminary design of a multiple-failure test apparatus, in which the effects of both Na and D/sub 2/O failures will be investigated, has been completed. Preliminary design of a mockup test apparatus has been finished; this apparatus, which will be a full scale representation of a section of the reactor, will be used to demonstrate the reliability of integrated Na and H/sub 2/O circulating systems under simulated normal and aggravated reactor operating conditions. The shielding problems associated with radiation limitations on access to header rooms for repairs and maintenance were evaluated. Temperatures, pressures, and flow rates for the secondary Na and steam systems were established. (auth)

• Research Organization: Nuclear Development Corp. of America, White Plains, N.Y.
• NSA Number: NSA-12-002517
• OSTI ID: 4318564
• Report Number(s): NDA-84-2
• Country of Publication: United States
• Language: English

Related Subjects

BARRIERS
COOLANT LOOPS
FAILURES
FLUID FLOW
HEAVY WATER
HEAVY WATER MODERATOR
LEAK DETECTORS
MOCKUP
PERSONNEL
PHYSICS
PLANNING
PRESSURE
RADIATION DOSES
REACTORS
SDR
SEPARATION PROCESSES
SHIELDING
SODIUM
STORAGE
TEMPERATURE
TUBES
VESSELS