SDR PROJECT QUARTERLY TECHNICAL PROGRESS REPORT FOR THE PERIOD AUGUST 1, 1957 THROUGH OCTOBER 31, 1957
Engineering design and experimental studies have been continued, with the objective of demonstrating the feasibility of separating Na and D/sub 2/O in the Sodium Deuterium Reactor (SDR). Fabrication methods for manufacturing SDR fuel-coolant tubes were examined; there is every indication that the design is feasible, and a good possibility that the tube can be formed in one piece, without welds. D/sub 2/O calandria design was backed up by visits to Chalk River and Savanaah River. A modified barrier arrangement has been studied and will be evaluated further. A Na leak detection system has heen outlined. Detailed design is proceeding on both static and fatigue rigs for testing the mechanical integrity of fuel-coolant tube and header joints. Screening tests on barrier materials were essentially completed, using the single-failure test apparatus at the NDA Pawling Laboratory. Results on Al were especially encouraging; two samples of 0.060-in- . thick Al were exposed to a jet of 950 deg F Na for more than 16 hr, and both survived. Design work has been completed, and fabrication is now proceeding, on the multiple-failure test apparatus, in which both H/sub 2/ O and Na system failures can be simulated at the same time. Detailed design is progressing on the mock-up test, which consists of three fuel-coolant tubes and associated barriers in a tank of water; this test will be used to demonstrate the reliability of integrated Na and H/sub 2/ O circulating systems under simulated reactor operating conditions. Additional analysis was done on the straight- through configuration, for two types of fuel elements-a U-Mo alloy, and UO/sub 2/. An alternative design concept, based on a slab configuration, was also studied; the slab design has some potential maintenance and safety advantages as compared with the calandria (or laffice) configuration. Shielding studies continued to concentrate on after-shutdown radiation levels in the header rooms. (For preceding period see NDA84-2.) (auth)
- Research Organization:
- Nuclear Development Corp. of America, White Plains, NY (United States)
- DOE Contract Number:
- AT(30-3)-256
- NSA Number:
- NSA-12-006192
- OSTI ID:
- 4310452
- Report Number(s):
- NDA-084-3
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-58
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
ALUMINUM- BARRIERS- CORROSION- FABRICATION- FAILURES- FLUID FLOW- HEAVY WATER- LIQUID FLOW- MATERIALS TESTING- MECHANICAL PROPERTIES- MOCKUP- PLANNING- REACTORS- SDR- SODIUM- TEMPERATURE- TESTING- WATER
CONFIGURATION- FABRICATION- FLUID FLOW- HEAVY WATER- LIQUID FLOW- MAINTENANCE- MECHANICAL PROPERTIES- PLANNING- PLATES- REACTOR CORE- REACTORS- SAFETY- SDR- SODIUM- TESTING- WATER
COOLANT LOOPS- DETECTION- FABRICATION- FATIGUE- FLUID FLOW- HEAVY WATER- IN PILE LOOPS- JOINTS- LEAKS- LIQUID FLOW- MECHANICAL PROPERTIES- MOCKUP- PLANNING- REACTORS- SDR- SODIUM- TESTING- TUBES- WATER
FABRICATION-