BRITL : A FUEL ROD ANALYTICAL MODEL FOR THERMAL OR FAST FLUX IRRADIATIONS

Author: Thompson, W. I
Published: United States : [publisher not identified], 1970.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1970.
Physical Description: microfiche : negative ; 11 x 15 cm

Availability

Finding items...

Report Numbers

GAMD-10007

Other Subject(s)

Britl-code
Computer programs/britl, for fast and thermal neutron effects on tensile stresses in mixed oxide rod type fuel elements
Computers
Digital systems
Fast neutrons
Fuel elements
N38910 -reactor theory-kinetics
Neutrons, fast/effects on tensile stresses in mixed oxide rod type fuel elements, britl computer program for
Neutrons, thermal/effects on tensile stresses in mixed oxide rod type fuel elements, britl computer program for
Oxides
Programming
Radiation effects
Reactor fuel elements/ radiation effects on tensile stresses in mixed oxide rod type, britl computer program for fast and thermal neutron
Rods
Tensile properties
Thermal neutrons
Thermal stresses

Collection

U.S. Atomic Energy Commission depository collection.

Note

DOE contract number: AT(04-3)-167
NSA number: NSA-24-033483
OSTI Identifier 4124141
Research organization: Gulf General Atomic, Inc., San Diego, CA (United States).

View MARC record | catkey: 45372189

Actions for BRITL : A FUEL ROD ANALYTICAL MODEL FOR THERMAL OR FAST FLUX IRRADIATIONS

BRITL : A FUEL ROD ANALYTICAL MODEL FOR THERMAL OR FAST FLUX IRRADIATIONS

Availability