reactor fuel

Study of a slightly enriched R reactor fuel by means of a pulsed neutron source.

Validation efforts for the neutronics of a plutonium-erbium-zirconium oxide inert matrix light water reactor fuel.

To protect the light-water reactor fuel supply, with thousands of centrifuge uranium enrichment plant is a modern operation.

It is pressing for U. S. permission to recycle plutonium from spent power-reactor fuel, originally supplied by the United States.

A third site that was once used as a storage centre for spent reactor fuel is now a brick-strewn wasteland.

Characterization of secondary products of uranium-aluminum material test reactor fuel element corrosion in repository-relevant brine.

Improvement of the homogeneity of atomized particles dispersed in high uranium density research reactor fuel.

In the meantime, fire trucks are spraying water to help cool reactor fuel rod pools.

Temperature and humidity effects on the corrosion of aluminium-base reactor fuel cladding materials during dry storage.

This will eventually allow India to extract plutonium from spent reactor fuel of American origin.

A combined method to evaluate the resonance self shielding effect in power fast reactor fuel assembly calculation.

Evaluation of corrosion of aluminum based reactor fuel cladding materials during dry storage.

Capability of ruthenium isotopes in distinguishing spent reactor fuel type and burnup.

Behavior of fission products zirconium and barium in fast reactor fuel irradiated to high burnup.

Research reactor fuel transport in the U. K.

But the going and froing over reactor fuel helps distract attention from Iran's refusal to come clean about its nuclear past.

Fission gas release and swelling model of metallic fast reactor fuel.

In all three cases, the problems have arisen after levels of water needed to cool reactor fuel rods fell.

Examination of spent pressurized water reactor fuel rods after 15 years in dry storage.

Liquid-metal-bonded gap for light water reactor fuel rods.

Economic analysis on direct use of spent pressurized water reactor fuel in CANDU reactors-1: DUPIC fuel fabrication cost.

Economic analysis on direct use of spent pressurized water reactor fuel in CANDU reactors-3: Spent DUPIC fuel disposal cost.

Monitoring fast neutron flux inside spent reactor fuel by CR-39 detector.

Reported that the No. 1 reactor fuel assemblies present level of 70% damage, 3 damage to the reactor protective shell.

And until 2022, for Unit 1 to 3 of reactor fuel rods melted recovery.

removing stocks of low-enriched uranium (which, enriched further, could make a bomb) for fashioning into reactor fuel abroad;

Research on Advanced Pressurized Water Reactor Fuel Management Calculation Method and Program Development

Development of a Monolithic Research Reactor Fuel Type at Argonne National Laboratory

Standard Specification for Wrought Zirconium Alloy Seamless Tubes for Nuclear Reactor Fuel Cladding

Radial Heat Transfer Mechanisms of Faulted Fast Reactor Fuel Subassembly During Local Accidents

Characteristic Ratios of Light-Water Reactor Fuel and Reactor Type of Spent Fuel

Assessment of Core Failure Limits for Light Water Reactor Fuel under Reactivity Initiated Accidents

The application of nonlinear iteration semi-analytic nodal method in CANDU reactor fuel management

Cellular automata approach to investigation of high burn-up structures in nuclear reactor fuel

Experimental Research on Velocity Distribution in Narrow Slots of Plane Type Reactor Fuel

Nuclear Reactor Fuel in Light Water Reactors, Methods of Measuring the Performance of

Romanian nuclear fuel fabrication and in-reactor fuel operational experience

Design Requirements for Light Water Reactor Fuel Handling Systems

Some tooling for manufacturing research reactor fuel plates

Application of Genetic Algorithm in Reactor Fuel Management

A safety check-up method for decommissioned reactor fuel element cladding

Reactor fuel charging and discharging machines;

Minimum cladding thickness of material test reactor fuel plates

ASI; international storage regime of spent reactor fuel;

Matrix for Light Water Reactor Fuel Reprocessing

Post-irradiation Examination of 10 MW High Temperature Gas-Cooled Reactor Fuel

Determining a pool - type reactor fuel policy

Development of low-strain resistant fuel for power reactor fuel rods