THE ARGONAUT REACTOR: A GENERALIZED REACTOR FACILITY FOR NUCLEAR TECHNOLOGY TRAINING AND RESEARCH

Technical Report · Fri Oct 31 04:00:00 EST 1958

OSTI ID:4306796

Lennox, D H; Spinrad, B I; Kelber, C N; Armstrong, R H; Kolb, W L

S>Argonaut is a 10-kw (max.) thermal reactor moderated by water and reflected by graphite. It is a flexible, low-cost facility designed primarily for instruction and research in reactor technology. Plate-type fuel elements are spaced with graphite wedges to form an angular core; thus various fuel patterns, from pseudoslab to multiple groups, can be effected. With 20% enriched fuel, the nominal critical mass is 3 6 kg U/sup 235/ in a double slab configuration. A graphite column within the fuel ring provides a large (2 ft OD by 4 ft high) region for internal exponentials, danger coefficient, and irradiation experiments. Surrounding the core region is a graphite reflector extended on one side to form a thermal column (5 ft square cross section). A movable tank for shielding or migration measurements faces one of the reflector sides. Stacked concrete block constitutes the main body of shieki, so that tunnels for large experiments or a second thermal column can be provided. The nuclear characteriatics of Argonaut make it seif-limiting in the BORAX manner. Measurements show the void and temperature coefficients to be negative: -0.25% k per void%, and -2 x 10/sup -4/ k deg C, respectively. The measured neutron lifetime is 220 mu sec. Routine control is by insertion of poison rods. Secondary safety is available through removal, and nitrogen injection to reduce moderator density. Total cost for construction of the reactor was ~ 0,000. A 20-minute color film showing design details and student participation in experimental uses is available. (auth)

• Research Organization: Argonne National Lab., Lemont, Ill.
• NSA Number: NSA-12-015052
• OSTI ID: 4306796
• Report Number(s): A/CONF.15/P/1019
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

BUILDINGS
CONCRETES
CONFERENCE
CONFIGURATION
CONTROL ELEMENTS
CRITICALITY
DENSITY
DIFFUSION LENGTH
ECONOMICS
FUEL ELEMENTS
GRAPHITE
INJECTION
IRRADIATION
LIFETIME
MASS
MATERIALS TESTING
MEASURED VALUES
MECHANICAL STRUCTURES
MODERATORS
NEUTRON BEAMS
NITROGEN
OPERATION
PERSONNEL
PHYSICS
PLANNING
PLATES
POISONING
REACTIVITY
REACTOR CORE
REACTOR SAFETY
REFLECTORS
RESEARCH REACTORS
RODS
SHIELDING
SHUTDOWN
SLOWDOWN
SPACERS
STABILITY
TEMPERATURE
THERMAL NEUTRONS
URANIUM 235
WATER MODERATOR
ZONES