Sipping tests have been performed for fuel elements of the TR-2 reactor at Çekmece Nuclear Research and Training Center (CNRTC), in order to find out which one failed in the core. A sipping assembly has been constructed and placed in the pool of the TR-2 reactor. The assembly identifies leaking fuel elements by collecting and measuring 137Cs that leak out from the defective fuel elements. 31 fuel elements in the reactor have been tested for the clad integrity. The measured 137Cs activity of the fuel element with an identification number S-104 is a 10247 Bq/(0.31). This value is approximately 234 times greater than the average of the other tested fuel elements in the reactor. © Carl Hanser Verlag, München
On March 11 and 12, 1958, the BORAX-IV reactor was operated at a power of 2.4 Mw, even though a larg...
Advanced Fuel Power-Limit Test. Fabrication of the 50 basic fuel assemblies has been completed. The ...
The current paper reports the results of gamma spectroscopic burn-up determination and KüFA safety t...
Sipping tests have been performed for fuel elements of the TR-2 reactor at Cekmece Nuclear Research ...
This work describes sipping tests performed on Material Testing Reactor (MTR) fuel elements of the I...
During a periodical activity of characterization of the ionic-exchange resins of the demineralizer o...
The present work continues the series of papers on the revision of the conventional technique for ev...
Fuel failures during operation of Nuclear Power Plants (NPPs) may lead to substantial economic losse...
On January 28th 2004, during a periodical activity of characterization of the ionic-exchange resins ...
In terms of safety and the efficient management of spent fuel storage, detecting failed fuel is one ...
In terms of safety and the efficient management of spent fuel storage, detecting failed fuel is one ...
The Heavy Water Component Test Reactor (HWCTR) facility is a pressurized heavy water reactor that wa...
A series of critical experiments were completed from 1962–1965 at Oak Ridge National Laboratory’s (O...
Fuel failures may occur during operation of nuclear power plants. One of the possible and most sever...
As a result of the accident on March 28, 1979, fuel debris was dispersed into the primary coolant sy...
On March 11 and 12, 1958, the BORAX-IV reactor was operated at a power of 2.4 Mw, even though a larg...
Advanced Fuel Power-Limit Test. Fabrication of the 50 basic fuel assemblies has been completed. The ...
The current paper reports the results of gamma spectroscopic burn-up determination and KüFA safety t...
Sipping tests have been performed for fuel elements of the TR-2 reactor at Cekmece Nuclear Research ...
This work describes sipping tests performed on Material Testing Reactor (MTR) fuel elements of the I...
During a periodical activity of characterization of the ionic-exchange resins of the demineralizer o...
The present work continues the series of papers on the revision of the conventional technique for ev...
Fuel failures during operation of Nuclear Power Plants (NPPs) may lead to substantial economic losse...
On January 28th 2004, during a periodical activity of characterization of the ionic-exchange resins ...
In terms of safety and the efficient management of spent fuel storage, detecting failed fuel is one ...
In terms of safety and the efficient management of spent fuel storage, detecting failed fuel is one ...
The Heavy Water Component Test Reactor (HWCTR) facility is a pressurized heavy water reactor that wa...
A series of critical experiments were completed from 1962–1965 at Oak Ridge National Laboratory’s (O...
Fuel failures may occur during operation of nuclear power plants. One of the possible and most sever...
As a result of the accident on March 28, 1979, fuel debris was dispersed into the primary coolant sy...
On March 11 and 12, 1958, the BORAX-IV reactor was operated at a power of 2.4 Mw, even though a larg...
Advanced Fuel Power-Limit Test. Fabrication of the 50 basic fuel assemblies has been completed. The ...
The current paper reports the results of gamma spectroscopic burn-up determination and KüFA safety t...