Cladding swelling and rupture models for LOCA analysis

View on Open Library

Cladding swelling and rupture models for LOCA analysis

by D. A. Powers

No reviews yet

First published: 1980 1 language

Subjects

Nuclear fuel claddings Cooling Accidents Pressurized water reactors Water cooled reactors

Reviews

Log in or sign up to write a review.

No reviews yet. Be the first!

More by D. A. Powers

Evaluation of simulated-LOCA tests that produced large fuel cladding ballooning

Evaluation of simulated-LOCA tests that ...

A simplified model of decontamination by BWR steam suppression pools

A simplified model of decontamination by...

A simplified model of aerosol removal by containment sprays

A simplified model of aerosol removal by...

A simplified model of aerosol scrubbing by a water pool overlying core debris interacting with concrete

A simplified model of aerosol scrubbing ...

Source term attenuation by water in the Mark I boiling water reactor drywell

Source term attenuation by water in the ...

Submission for the CSNI/GREST benchmark exercise on chemical thermodynamic modeling in core-concrete interaction releases of radionuclides

Submission for the CSNI/GREST benchmark ...

You Might Also Like

More in Nuclear fuel claddin...

In-pile observation of fuel and clad relocation during LMFBR core-disruptive accidents

In-pile observation of fuel and clad rel...

S. A. Wright

Evaluation of simulated-LOCA tests that produced large fuel cladding ballooning

Evaluation of simulated-LOCA tests that ...

D. A. Powers

Zirconium in the nuclear industry

Zirconium in the nuclear industry

International Symposium on Zirconium in the Nuclear Industry (15th 2007 Sunriver, Or.)

Zirconium in the nuclear industry

Zirconium in the nuclear industry

Gerry D. Moan

Report of an investigation into deterioration of the Plutonium Fuel Form Fabrication Facility (PuFF) at the DOE Savannah River Site

Report of an investigation into deterior...

United States. Dept. of Energy.

Zirconium in the Nuclear Industry

Zirconium in the Nuclear Industry

Craig M. Eucken