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Improving reactor safety systems using component redundancy allocation technique

Habib A., Ashry H., Shokr A., Dakhly A.

Nukleonika

2005

Vol. 50, nr 3

105-112

This paper addresses the improvements to the reliability of the safety systems of nuclear reactors using redundancy allocation technique. The study has been carried out using the Probabilistic Safety Assessment (PSA). PSA involves, among others, the use of fault and event tree tools in the evaluation of the safety system failure probabilities and the quantification of annual occurrence probability of the accidental conditions postulated in the design of the nuclear reactors. The PSA has been presented and discussed. The Egypt Second Research Reactor, ETRR-2, has been used as a case study. The failure probability of the already existing safety systems has been reviewed. The effect of the allocation of more redundant components to the existing safety systems on the failure probability of the systems has been evaluated. The event trees for two selected initiating events, from those events postulated in the ETRR-2 design, have been studied considering the allocation of more redundant components to the safety systems. The result of the study showed that further improvement could be introduced to the reliability of the Confinement Ventilation System (CVS).

Analysis of thermal neutron flux measurement in the Cobalt Irradiation Device at ETRR-2

Abou-Zaid A.

Nukleonika

2003

Vol. 48, nr 4

211-214

The measurements of geometrical distribution of thermal neutron flux in research reactors are often used in the field of reactor operation and reactor physics. Usually such measurements are carried out by using the gold wire activation method. This method has been used for measuring a thermal neutron flux at the location of a Cobalt Irradiation Device (CID) of ETRR-2. A special device was used for locating samples in an irradiation box and the measurements were performed for seventy-two positions. The Monte Carlo MCNP-4B code has been used for the modeling and simulation of ETRR-2 core with structural materials and surrounding beryllium reflectors. The device used in the flux measurement was also simulated in the MCNP-4B model. The thermal flux has been calculated and compared with the experimental one. The results show good agreement between the measured and calculated flux.