Comparisons of measured and calculated LWR fuel rod responses during a reactivity initiated accident test are presented. The results indicate that the computer code, FRAP-T5, adequately calculates the fuel rod behavior up to the time at which the gap closes and provides a good thermal solution up to the time of gross fuel and cladding relocation. Three areas have been identified for further model development: (a) development of a fuel swelling model for near molten fuel temperatures; (b) incorporation of a deformable fuel pellet model that is applicable for the closed gap, high strain rate regime; and (c) expansion of the failure stress data base to include heat-up rates of up to 5000 K/s
During the normal operation of a Light Water Reactor (LWR), the fuel–cladding gap may close, as a re...
An integrated computer model for reactor fuel cladding rupture under loss-of-coolant accident (LOCA)...
Test L5 simulated a hypothetical loss-of-flow accident in an LMFBR using three (plutonium, uranium) ...
Light water reactor (LWR) fuel rod behavior during transient experiments conducted in the Power Burs...
This paper presents an assessment of LWR fuel damage during a reactivity initiated accident and comm...
An analysis of fuel rod behavior during reactivity initiated accidents is presented. The calculation...
A nuclear reactor systems code has the ability to model the system response in an accident scenario ...
A nuclear reactor systems code has the ability to model the system response in an accident scenario ...
The fuel irradiation and burnup causes geometrical and dimensional changes in the fuel rod which ...
Prediction of the behavior of LWR fuel rods and fission products under off-normal and accident condi...
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 20...
Three similar experiments conducted to support the analyses of hypothetical LMFBR unprotected-loss-o...
This is the final report on the resu1ts of the FR2 In-pile Experiments on LWR (Light Water Reactor) ...
The analysis of the behavior of light water reactor (LWR) fuel rods is described.The properties of r...
During the normal operation of a Light Water Reactor (LWR), the fuel–cladding gap may close, as a re...
During the normal operation of a Light Water Reactor (LWR), the fuel–cladding gap may close, as a re...
An integrated computer model for reactor fuel cladding rupture under loss-of-coolant accident (LOCA)...
Test L5 simulated a hypothetical loss-of-flow accident in an LMFBR using three (plutonium, uranium) ...
Light water reactor (LWR) fuel rod behavior during transient experiments conducted in the Power Burs...
This paper presents an assessment of LWR fuel damage during a reactivity initiated accident and comm...
An analysis of fuel rod behavior during reactivity initiated accidents is presented. The calculation...
A nuclear reactor systems code has the ability to model the system response in an accident scenario ...
A nuclear reactor systems code has the ability to model the system response in an accident scenario ...
The fuel irradiation and burnup causes geometrical and dimensional changes in the fuel rod which ...
Prediction of the behavior of LWR fuel rods and fission products under off-normal and accident condi...
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 20...
Three similar experiments conducted to support the analyses of hypothetical LMFBR unprotected-loss-o...
This is the final report on the resu1ts of the FR2 In-pile Experiments on LWR (Light Water Reactor) ...
The analysis of the behavior of light water reactor (LWR) fuel rods is described.The properties of r...
During the normal operation of a Light Water Reactor (LWR), the fuel–cladding gap may close, as a re...
During the normal operation of a Light Water Reactor (LWR), the fuel–cladding gap may close, as a re...
An integrated computer model for reactor fuel cladding rupture under loss-of-coolant accident (LOCA)...
Test L5 simulated a hypothetical loss-of-flow accident in an LMFBR using three (plutonium, uranium) ...