Add to ORKGAn analysis of fuel rod behavior during reactivity initiated accidents is presented. The calculational approach is described, predictions are discussed and compared to data from the SPERT power excursion tests, and the sensitivity of maximum cladding temperatures to initial reactor conditions, enthalpy insertions, and other experiment design parameters is investigated. 10 references. (auth
This document describes the experiment operating specifications for the Reactivity Initiated Acciden...
This paper describes a new approach to define an analytical fuel rod cladding failure criterion duri...
The results of the pretest analyses for Test RIA 1-4 are presented. Test RIA 1-4 consists of a 3x3 a...
Comparisons of measured and calculated LWR fuel rod responses during a reactivity initiated accident...
The fuel irradiation and burnup causes geometrical and dimensional changes in the fuel rod which ...
Light water reactor (LWR) fuel rod behavior during transient experiments conducted in the Power Burs...
An assessment is made of recent test data from France, Japan, and Russia, and of earlier test data f...
This paper presents an assessment of LWR fuel damage during a reactivity initiated accident and comm...
Hypothetical transients and accidents are used in the design and safety analysis of light-water reac...
ANALYSIS OF UNCONTROLLED REACTIVITY INSERTION TRANSIENT OF TRIGA MARK 2000 BANDUNG USING MTR PLATE T...
The analysis of the behavior of light water reactor (LWR) fuel rods is described.The properties of r...
In the context of more and more demanding reactor managements, the fuel assembly discharge burn-up i...
In the context of more and more demanding reactor managements, the fuel assembly discharge burn-up i...
The response of fuel in a boiling water reactor to the rod drop accident (RDA) was studied using the...
The results of Spert I in-pile transient tests of a rodtype, low- enrichment UO/sub 2/ fuel element ...
This document describes the experiment operating specifications for the Reactivity Initiated Acciden...
This paper describes a new approach to define an analytical fuel rod cladding failure criterion duri...
The results of the pretest analyses for Test RIA 1-4 are presented. Test RIA 1-4 consists of a 3x3 a...
Comparisons of measured and calculated LWR fuel rod responses during a reactivity initiated accident...
The fuel irradiation and burnup causes geometrical and dimensional changes in the fuel rod which ...
Light water reactor (LWR) fuel rod behavior during transient experiments conducted in the Power Burs...
An assessment is made of recent test data from France, Japan, and Russia, and of earlier test data f...
This paper presents an assessment of LWR fuel damage during a reactivity initiated accident and comm...
Hypothetical transients and accidents are used in the design and safety analysis of light-water reac...
ANALYSIS OF UNCONTROLLED REACTIVITY INSERTION TRANSIENT OF TRIGA MARK 2000 BANDUNG USING MTR PLATE T...
The analysis of the behavior of light water reactor (LWR) fuel rods is described.The properties of r...
In the context of more and more demanding reactor managements, the fuel assembly discharge burn-up i...
In the context of more and more demanding reactor managements, the fuel assembly discharge burn-up i...
The response of fuel in a boiling water reactor to the rod drop accident (RDA) was studied using the...
The results of Spert I in-pile transient tests of a rodtype, low- enrichment UO/sub 2/ fuel element ...
This document describes the experiment operating specifications for the Reactivity Initiated Acciden...
This paper describes a new approach to define an analytical fuel rod cladding failure criterion duri...
The results of the pretest analyses for Test RIA 1-4 are presented. Test RIA 1-4 consists of a 3x3 a...