Öz
A transient-state thermal hydraulics analysis of the TRIGA burn core of the TRIGA Mark II research reactor has been conducted using PARET/ANL. This study covers the calculation of safety parameters due to large reactivity insertions at low operating power. The peak power and energy for the burn core have been calculated, whose values were found to be lower than those of the beginning of the cycle (BOC) core. Moreover, the safety parameters of DNBR and clad temperature maintain well margins with the Safety Analysis Report. No nucleate boiling was observed in the hottest fuel. Hence, the burn core can be safely utilized for pulsing operation.
Anahtar Kelimeler
Kaynakça
- Hossain S M, Zulquarnain M A, Kamal, I and Islam M N (2011). Current Status and Perspectives of Nuclear Reactor Based Research in Bangladesh, IAEA, Vienna, 7-14. IAEA-TECDOC-1659
- Mizanur Rahman M M, Akond, M A R, Basher M K, and Huda M Q (2014). Steady State Thermal Hydraulic Analysis of TRIGA Research Reactor, World Journal of Nuclear Science and Technology, 81-87
- Huda M Q and Rahman M (2004). Thermo-Hydrodynamic Design and Safety Parameter Studies of the TRIGA MARK II Research Reactor, Annals of Nuclear Energy, 31, 1101-1118
- Altaf M H and Badrun N H (2014).Thermal Hydraulic Analysis of 3 MW TRIGA Research Reactor of Bangladesh Considering Different Cycles of Burnup, Atom Indonesia, 40(3), 107-112.
- General Atomics (1979), 10 MW TRIGA-LEU Fuel and Reactor Design Description. General Atomics, San Diego.
- Obenchain, C F, PARET (1969)-A Program for the Analysis of Reactor Transients. IDO-17282, Idaho Atomic Energy.
- Mahmood M S et al. (2012), Individual Fuel Element Burnup of BAEC TRIGA Core, Technical Report, INST-RPED-RARD-01/009.
- FSAR (2006), Final Safety Analysis Report for 3 MW TRIGA MARK-II Research Reactor at AERE, Savar, Dhaka, Bangladesh. BAEC, Dhaka.
- Huda, M Q, Bhuiyan, S I, Chakroborty, T K, Sarker, M M and Mondal, M A W (2001). Thermal Hydraulic Analysis of the 3 MW TRIGA MARK-II Research Reactor under steady state and transient state conditions. Nuclear Technology, 135, 51-66
- Altaf M H, Badrun N H and Khan M J H (2014). Validation of EUREKA-2/RR Code for Analysis of Pulsing Parameters of TRIGA Mark II Research Reactor in Bangladesh, The nucleus, 53(3), 385-389
Öz
A transient-state thermal hydraulics analysis of the TRIGA burn core of the TRIGA Mark II research reactor has been conducted using PARET/ANL. This study covers the calculation of safety parameters due to large reactivity insertions at low operating power. The peak power and energy for the burn core have been calculated, whose values were found to be lower than those of the beginning of the cycle (BOC) core. Moreover, the safety parameters of DNBR and clad temperature maintain well margins with the Safety Analysis Report. No nucleate boiling was observed in the hottest fuel. Hence, the burn core can be safely utilized for pulsing operation.
Anahtar Kelimeler
Kaynakça
- Hossain S M, Zulquarnain M A, Kamal, I and Islam M N (2011). Current Status and Perspectives of Nuclear Reactor Based Research in Bangladesh, IAEA, Vienna, 7-14. IAEA-TECDOC-1659
- Mizanur Rahman M M, Akond, M A R, Basher M K, and Huda M Q (2014). Steady State Thermal Hydraulic Analysis of TRIGA Research Reactor, World Journal of Nuclear Science and Technology, 81-87
- Huda M Q and Rahman M (2004). Thermo-Hydrodynamic Design and Safety Parameter Studies of the TRIGA MARK II Research Reactor, Annals of Nuclear Energy, 31, 1101-1118
- Altaf M H and Badrun N H (2014).Thermal Hydraulic Analysis of 3 MW TRIGA Research Reactor of Bangladesh Considering Different Cycles of Burnup, Atom Indonesia, 40(3), 107-112.
- General Atomics (1979), 10 MW TRIGA-LEU Fuel and Reactor Design Description. General Atomics, San Diego.
- Obenchain, C F, PARET (1969)-A Program for the Analysis of Reactor Transients. IDO-17282, Idaho Atomic Energy.
- Mahmood M S et al. (2012), Individual Fuel Element Burnup of BAEC TRIGA Core, Technical Report, INST-RPED-RARD-01/009.
- FSAR (2006), Final Safety Analysis Report for 3 MW TRIGA MARK-II Research Reactor at AERE, Savar, Dhaka, Bangladesh. BAEC, Dhaka.
- Huda, M Q, Bhuiyan, S I, Chakroborty, T K, Sarker, M M and Mondal, M A W (2001). Thermal Hydraulic Analysis of the 3 MW TRIGA MARK-II Research Reactor under steady state and transient state conditions. Nuclear Technology, 135, 51-66
- Altaf M H, Badrun N H and Khan M J H (2014). Validation of EUREKA-2/RR Code for Analysis of Pulsing Parameters of TRIGA Mark II Research Reactor in Bangladesh, The nucleus, 53(3), 385-389
Ayrıntılar
| Birincil Dil | İngilizce |
|---|---|
| Konular | Nükleer Mühendisliği (Diğer) |
| Bölüm | Araştırma Makalesi |
| Yazarlar | |
| Yayımlanma Tarihi | 29 Haziran 2025 |
| Gönderilme Tarihi | 8 Nisan 2025 |
| Kabul Tarihi | 13 Haziran 2025 |
| Yayımlandığı Sayı | Yıl 2025 Cilt: 38 Sayı: 1 |
