SRE POWER EXPANSION PROGRAM CORE MODIFICATIONS AND CORE III FUEL. TITLE I

Technical Report · Sun Sep 01 04:00:00 EDT 1963

OSTI ID:4623123

Noyes, R C

Designs were developed for new core components required to modify the SRE core to accomplish the objectives of the PEP program. The reactor is to be operated initially at 30 Mw(t) at a mixed-mean outlet temperature of 1192 deg F with a 33 element loading of hypostoichiometric uranium monocarbide fuel. New Zircaloy-2 canned moderator elements were designed which will operate at an outlet temperature of 1200 deg F and which will allow adequate moderator cooling for core powers up to 40 Mw(t). Dry control rods and thimbles were designed to permit increased heating rates. Two types of fuel elements were designed to accomplish the dual objectives of irradiating fuel rods at both ASCR maximum temperatures and power densities, and at maximum temperatures and power densities significantly in excess of ASCR conditions. Thirty standard fuel elements of 8- rod clusters of 0.60-in., 6.5%-enriched slugs are to function both as driver elements and test elements. The four test elements of this type will be located in the first fuel ring and will operate at a maximum nominal centerline temperature of 1717 deg F and average specific power of 35.1 kw/kgU. At 80% load factor, these test elements will achieve 25,000 Mwd/MTU average burnup in 30 months. The 26 driver elements will require replacements twice during this period to maintain reactivity. Three special fuel elements consisting of 8-rod clusters 0.50-in., 15%enriched fuel slugs are to be located in the center position and first fuel ring. Fuel in these elements will be irradiated at a maximum nominal centerline temperature of 1905 deg F and average specific power of 65.6 kw/kgU. At 80% load factor these elements will achieve 25,000 Mwd/MTU average burnup in 18 months. (auth)

• Research Organization: Atomics International. Div. of North American Aviation, Inc., Canoga Park, Calif.
• DOE Contract Number: AT(11-1)-GEN-8
• NSA Number: NSA-17-042347
• OSTI ID: 4623123
• Report Number(s): NAA-SR-Memo-8734
• Country of Publication: United States
• Language: English

Related Subjects

BURNUP
CANNING
CONTROL ELEMENTS
COOLING
FUEL ELEMENTS
FUELS
HEATING
IRRADIATION
MODERATORS
OPERATION
PLANNING
POWER
POWER PLANTS
REACTIVITY
REACTOR CORE
REACTOR TECHNOLOGY
SRE
URANIUM CARBIDES
ZIRCALOY