Spert Progress Report July, August, September 1957

Technical Report · Tue Oct 01 04:00:00 EDT 1957

DOI:https://doi.org/10.2172/4311361· OSTI ID:4311361

Nyer, W. E. ^[1]; Bright, G. O. ^[1]

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1. Phillips Petroleum Co., Idaho Falls, ID (United States). Atomic Energy Div.

Spert--I-- A brief resume of "A'" core experiments is presented and the results of some of the static measurements with the "B" core are shown. It was found that four usable cores are possible with the removable-plate "B'' fuel assemblies. The measurements made to date have been with a 24 fuel plate/ assembly, 32 assembly core, and include rod worth, flux distribution, temperature coefficient and preliminary void coefficient studies. Spert--II-- The construction contract was let and construction started in August. Spert--III -- The control system circuit drawings are essentially complete. Data Reduction and Interpretation-- The progress made in reducing the large raw data backlog from the Spert I "A" core experiments is shown. Work is continuing on the calculation of reactivity behavior during a transient, with the principal area of investigation being that of a boiling or slightiy subcooled experiments. The use of other calculational procedures as a check on the reactivity behavior work is being investigated. Theoretical-- The critical masses for the various possible "B'' cores were calculated, and agree quite well with the experimentally determined values. Some machine calculations of the temperature and void effect with the 32 assembly core were made, but no direct comparison with empirical values is yet possible. Two theoretical formulations, one a refinement of the Fuchs' model for reactor self-shutdown which seeks to explain the initial reactor transient behavior, and one which endeavors to show that the shutdown mechanism for reactor periods longer than 50 milliseconds can be ascribed to moderator density changes, were evolved. Instrumentation--The primary activities of the Instrumentation section were directed toward completion of all modification, maintenance, installation, and calibration of instrumentation necessary for performing static and transient tests on the Spert--I B'' core. Engineering-- Various modifications were made of the Spert--I reactor, including a new mechanism for clamping the fuel assembly in the core. Corrosion studies on Al were made for the Spert--I and Spert--II cores. A program is underway to determine a suitable control rod construction for Spert--II. Flow tests were made on Spert-- II and Spert -- III fuel assemblies. A complete description of the Spert--III control rod test facility is given. The results of the tests which have been made in this facility show that the present design of the Spert-- III control rods and drives is satisfactory. An engineering completion schedule is given for both Spert--II and Spert--III. (For preceding period see (IDO- 16415.) (auth)

• Research Organization: Phillips Petroleum Co., Idaho Falls, ID (United States). Atomic Energy Div.
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Atomic Energy Commission (AEC)
• DOE Contract Number: AT(10-1)-205
• NSA Number: NSA-12-004998
• OSTI ID: 4311361
• Report Number(s): IDO--16416
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ALUMINUM-- CONTROL ELEMENTS-- CORROSION-- FLUID FLOW-- FUEL ELEMENTS-- INSTRUMENTS-- MAINTENANCE-- MECHANICAL STRUCTURES-- PLANNING-- REACTOR CORE-- REACTORS-- SERVOMECHANISMS-- SPERT-1-- SPERT-2-- SPERT-3-- STANDARDS-- TESTING
BOILING-- BUBBLES-- COMPUTERS-- CONFIGURATION-- CONTROL SYSTEMS-- DISTRIBUTION-- ELECTRONICS-- FUEL ELEMENTS-- MATHEMATICS-- MEASURED VALUES-- NEUTRON FLUX-- PLANNING-- REACTIVITY-- REACTOR CORE-- REACTORS-- SPERT-1-- SPERT-2-- SPERT-3-- TEMPERATURE-- TEMPERATURE COEFFICIENT-- VARIATIONS- - VOID COEFFICIENT
BUBBLES-- COMPUTERS-- CRITICALITY-- DENSITY-- MATHEMATICS-- MODERATORS-- REACTIVITY-- REACTORS-- SHUTDOWN-- SPE
Fuel Plate
Maintenance
Nuclear Criticality Safety Program (NCSP)
Reactor
Spert I
Spert II
Spert III