The Leaking Fuel Experiment test facility was designed to simulate the activity release from spent leaking fuel rods under steady state and transient conditions in the spent fuel pool. The experimental rig included an electrically heated fuel rod with different defects and a cooling system. The fission product transport was simulated by potassium-chloride. The conductivity changes of the water in the cooling system were measured to provide information about the amount of released solution. Defects of different sizes and positions were applied, together with a wide range of rod powers to simulate decay heat. The produced data can be used for predicting the activity release from leaking fuel under storage conditions and for the interpretation...
In cases of fuel failure in irradiated nuclear fuel assemblies, causing leakage of fission gasses fr...
The substantial release of fission gas during temperature transients (burst release) can be critical...
A 3-dimensional (3D) fuel performance analysis program, able to simulate normal operating conditions...
During reactor operation the fission gases Kr and Xe are formed within the UO2 matrix of nuclear fue...
Tests were conducted to determine the amount of moisture contained in breached, water-logged spent f...
Analysis of release data obtained during High Burnup Fuel Test 10 (HBU-10) has been completed. In th...
Fuel failures may occur during operation of nuclear power plants. One of the possible and most sever...
A physics-based model is developed for analysing the coupled phenomena of fission gas swelling and r...
This paper presents simulations of four tests performed on medium to high burnup fuel during the VER...
The consequences of potential accidents causing spent fuel rod failure may involve fuel particles re...
Nuclear fuel undergoes various changes in its properties and composition as it is irradiated in a nu...
The instant release of fission products from high burn-up UO2 fuels and one MOX fuel was investigate...
Experiences with an advanced spent nuclear fuel management in Slovakia are presented in this paper. ...
Preliminary tests are being conducted to evaluate the effectiveness of defected cladding as a barrie...
A description is given of an out-of-pile experiment which simulated fission-gas release in current-d...
In cases of fuel failure in irradiated nuclear fuel assemblies, causing leakage of fission gasses fr...
The substantial release of fission gas during temperature transients (burst release) can be critical...
A 3-dimensional (3D) fuel performance analysis program, able to simulate normal operating conditions...
During reactor operation the fission gases Kr and Xe are formed within the UO2 matrix of nuclear fue...
Tests were conducted to determine the amount of moisture contained in breached, water-logged spent f...
Analysis of release data obtained during High Burnup Fuel Test 10 (HBU-10) has been completed. In th...
Fuel failures may occur during operation of nuclear power plants. One of the possible and most sever...
A physics-based model is developed for analysing the coupled phenomena of fission gas swelling and r...
This paper presents simulations of four tests performed on medium to high burnup fuel during the VER...
The consequences of potential accidents causing spent fuel rod failure may involve fuel particles re...
Nuclear fuel undergoes various changes in its properties and composition as it is irradiated in a nu...
The instant release of fission products from high burn-up UO2 fuels and one MOX fuel was investigate...
Experiences with an advanced spent nuclear fuel management in Slovakia are presented in this paper. ...
Preliminary tests are being conducted to evaluate the effectiveness of defected cladding as a barrie...
A description is given of an out-of-pile experiment which simulated fission-gas release in current-d...
In cases of fuel failure in irradiated nuclear fuel assemblies, causing leakage of fission gasses fr...
The substantial release of fission gas during temperature transients (burst release) can be critical...
A 3-dimensional (3D) fuel performance analysis program, able to simulate normal operating conditions...