PHYSICS DATA FROM A MOCKUP OF THE HWCTR LATTICE IN THE PDP

Technical Report · Mon Feb 01 00:00:00 EST 1960

OSTI ID:4818312

Graves, W E

Experiments were performed in the Process Development Pile (PDP) with a critical mockup of the Heavy Water Components Test Reactor (HWCTR) lattice. Reactivity measurements served to determine control rod worths, the temperature coefficient of the reactor at low temperatures, the dependence of k/sub eff/ on concentrations of U/sup 235/ and poisons in the driver'' region of the reactor, and the charges in k/sub eff/ that occur in certain conceivable accidents in the HWCTR. Flux distribution measurements were made to determine over-all flux shapes, local flux variations around individual components, azimuthal flux variations due to asymmetrical combinations of control rods, and vertical flux variations obtainable through the use of control rods of partial length. Sufficiently detailed flux measurements were made to permit the calculation of neutron economy tables and to determine the neutron leakage from the reactor. Suitable adjustments in the input parameters made it possible to fit the experimental results with a two-group calculation. (auth)

• Research Organization: Du Pont de Nemours (E.I.) & Co. Savannah River Lab., Aiken, S.C.
• DOE Contract Number: AT(07-2)-1
• NSA Number: NSA-16-008310
• OSTI ID: 4818312
• Report Number(s): DP-457
• Resource Relation: Other Information: Orig. Receipt Date: 31-DEC-62
• Country of Publication: United States
• Language: English

Related Subjects

REACTOR TECHNOLOGY
ACCIDENTS
BUCKLING
BURNUP
CONFIGURATION
CONTROL ELEMENTS
CRITICAL ASSEMBLIES
CRITICALITY
DISTRIBUTION
EQUATIONS
EXCURSIONS
FAST NEUTRONS
GROUP THEORY
HEAVY WATER
HWCTR
LEAKS
LOSSES
LOW TEMPERATURE
MASS
MATERIALS TESTING
MEASURED VALUES
MOCKUP
MULTIPLICATION FACTORS
NEUTRON FLUX
NUMERICALS
PDP
POISONING
REACTIVITY
REACTOR CORE
REACTORS
RODS
SHUTDOWN
STANDARDS
TEMPERATURE
THERMAL NEUTRONS
TRANSIENTS
URANIUM 235
VARIATIONS