| Autor: |
Salah Ud-Din Khan, Shahab Ud-Din Khan |
| Rok vydání: |
2013 |
| Předmět: |
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| Popis: |
In this paper, we have developed a mathematical model for the nuclear reactor analysis to be implemented in the nuclear reactor code. THEATRe is nuclear reactor analysis code which can only work for the cylindrical type fuel reactor and cannot applicable for the plate type fuel nuclear reactor. Therefore, the current studies encompasses on the modification of THEATRe code for the plate type fuel element. This mathematical model is applicable to the thermal analysis of the reactor which is very important to determine the design of the reactor. It can produce desired thermal power without exceeding limitations on core components which may leads to fuel failure and radioactive release into the environment. The result obtained from modified code agrees well with other codes conforming the accuracy of simulation. |
| Databáze: |
OpenAIRE |
| Externí odkaz: |
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