On March 11 and 12, 1958, the BORAX-IV reactor was operated at a power of 2.4 Mw, even though a large number of the fuel elements contained defects through the cladding. Subsequent investigation showed that 22 of the fuel elements in the reactor contained one or more ruptured rods. During operation, radiation fields in the vicinity of the turbine and condenser were high, but on shutdown all radiation levels decayed rapidly with a 30-min half life and after 12 hr all parts of the turbine and condenser showed only normal radiation levels of a few mr/hr. The effluent gases, the reactor steam, the condensate, and the reactor water were sampled during steady operation and analyzed for fission product gases and other fission products. An analysis...
Sipping tests have been performed for fuel elements of the TR-2 reactor at Çekmece Nuclear Research ...
An analysis of the self-limitation of power excursions by steam production in heterogeneous water-mo...
The central aspect of the safety philosophy for a small HTR is the retention of fission products, pa...
"AEC Research and Development Report""(TID-4500, 15th Ed.)"Reactors - Power""October, 1959."Includes...
Reactor Programs. The design of the Boiling Experimental Reactor is described. The Borax-1 reactor w...
A description is given of the development and testing of a monitoring system which announces and ana...
The Phebus Fission Product Programme studies key phenomena and phenomenology of severe accidents in ...
During a periodical activity of characterization of the ionic-exchange resins of the demineralizer o...
ThO/sub 2/-UO/sub 2/ fuels have been studied because of certain advantages possessed by this type of...
Research and development on metallurglcal aspects of pressurized-water systems is summarized. A surv...
The diffusion of fission products out of the fuel elements leads to increased shielding requirements...
Research and development progress specifically directed toward the construction of a 40-Mw(e) protot...
On January 28th 2004, during a periodical activity of characterization of the ionic-exchange resins ...
International audienceDuring the irradiation of nuclear fuel in a light water reactor (LWR), fission...
Fuel failures during operation of Nuclear Power Plants (NPPs) may lead to substantial economic losse...
Sipping tests have been performed for fuel elements of the TR-2 reactor at Çekmece Nuclear Research ...
An analysis of the self-limitation of power excursions by steam production in heterogeneous water-mo...
The central aspect of the safety philosophy for a small HTR is the retention of fission products, pa...
"AEC Research and Development Report""(TID-4500, 15th Ed.)"Reactors - Power""October, 1959."Includes...
Reactor Programs. The design of the Boiling Experimental Reactor is described. The Borax-1 reactor w...
A description is given of the development and testing of a monitoring system which announces and ana...
The Phebus Fission Product Programme studies key phenomena and phenomenology of severe accidents in ...
During a periodical activity of characterization of the ionic-exchange resins of the demineralizer o...
ThO/sub 2/-UO/sub 2/ fuels have been studied because of certain advantages possessed by this type of...
Research and development on metallurglcal aspects of pressurized-water systems is summarized. A surv...
The diffusion of fission products out of the fuel elements leads to increased shielding requirements...
Research and development progress specifically directed toward the construction of a 40-Mw(e) protot...
On January 28th 2004, during a periodical activity of characterization of the ionic-exchange resins ...
International audienceDuring the irradiation of nuclear fuel in a light water reactor (LWR), fission...
Fuel failures during operation of Nuclear Power Plants (NPPs) may lead to substantial economic losse...
Sipping tests have been performed for fuel elements of the TR-2 reactor at Çekmece Nuclear Research ...
An analysis of the self-limitation of power excursions by steam production in heterogeneous water-mo...
The central aspect of the safety philosophy for a small HTR is the retention of fission products, pa...