التفاصيل البيبلوغرافية
| العنوان: |
Numerical investigation on heat flux variation in fuel bundle on circumferential temperature over fully voided channel of IPHWR. |
| المؤلفون: |
Kashyap, Ishan, Kumar, Sidharth, Singh, Saurav Kumar, Sharma, Mukesh |
| المصدر: |
AIP Conference Proceedings; 2023, Vol. 2863 Issue 1, p1-8, 8p |
| مصطلحات موضوعية: |
HEAT flux, HEAVY water reactors, TEMPERATURE distribution, NUCLEAR power plants, TEMPERATURE |
| مستخلص: |
To study the temperature behaviour of a single nuclear channel in voided condition for 220 MWe nuclear power plant based on Indian pressurised heavy water reactor (IPHWR), a thermal analysis with an assumption of steady state condition is performed. The temperature behaviour was noted for three different heat flux inputs which are 1000 W/m2, 2000 W/m2 and 3000 W/m2 respectively. Variation in circumferential and axial temperature distributions were studied for both Pressure tube (PT) and Calandria tube (CT) while they are in a concentric condition. Difference in temperature between points at 90° and 270° on the pressure tube and calandria tube were also observed to find out deviation in temperature between top and bottom of both the tubes. The effect of input heat flux on the moderator temperature near the calandria tube was also studied. [ABSTRACT FROM AUTHOR] |
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| قاعدة البيانات: |
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