Impact of CHF Correlations on DNBR of the TRIGA Mark II Research Reactor under different operational modes and burn-up conditions
Author affiliations
DOI:
https://doi.org/10.15625/0868-3166/21959Keywords:
PARET/ANL, Thermal hydraulics, BurnupAbstract
Departure from Nucleate Boiling Ratio (DNBR) is a crucial thermal hydraulics safety parameter for nuclear reactors. Hence selecting appropriate DNBR correlation is vital for design, licence and operation. The Bernath, Misrak, and Tong correlations have been utilized in PARET/ANL code in this study to calculate DNBR in TRIGA Mark II research reactor during both steady state and transient conditions, spanning from the beginning of cycle (BOC) to 1000 MWD of operation life. The findings reveal that the Bernath correlation consistently yields the lowest values across all operational phases compared to the Misrak and Tong correlations. Remarkably, the results obtained from the Bernath correlation align with the recommendations put forth by the General Atomics (GA) and Safety Analysis Report. Consequently, it is deemed suitable for application throughout all modes of reactor operation.
Downloads
Metrics
References
S. M. Hossain, M. A. Zulquarnain, I. Kamal, M. N. Islam, Current Status and Perspectives of Nuclear Reactor Based Research in Bangladesh, IAEA (2011) 7–14.
L. Bernath, A Theory of Local-Boiling Burnout and Its Application to Existing Data, Chem. Eng. Prog. Symp. Ser. 56 (1960) 95.
L. S. Tong, H. B. Currin, A. G. Thorp, New Correlations Predict DNB Conditions, Nucleonics 21 (1963) No. 5.
S. Mirshak, W. S. Durant, R. H. Towell, Heat Flux at Burnout, E. I. du Pont de Nemours & Co., Technical Report DP-355 (1959).
S. Chatzidakis, A. Ikonomopoulos, S. E. Day, PARET-ANL Modeling of a SPERT-IV Experiment under Different Departure from Nucleate Boiling Correlations, Nucl. Technol. 177 (2012) 119–131.
Bangladesh Atomic Energy Commission (BAEC), Final Safety Analysis Report for 3 MW TRIGA MARK-II Research Reactor at AERE, Savar, Dhaka, Bangladesh, BAEC, Dhaka (2006).
M. M. Mizanur Rahman, M. A. R. Akond, M. K. Basher, M. Q. Huda, Steady State Thermal Hydraulic Analysis of TRIGA Research Reactor, World J. Nucl. Sci. Technol. (2014) 81–87.
M. Q. Huda, M. Rahman, Thermo-Hydrodynamic Design and Safety Parameter Studies of the TRIGA MARK II Research Reactor, Ann. Nucl. Energy 31 (2004) 1101–1118.
General Atomics, 10 MW TRIGA-LEU Fuel and Reactor Design Description, General Atomics, San Diego (1979).
C. F. Obenchain, PARET—A Program for the Analysis of Reactor Transients, IDO-17282, Idaho Atomic Energy (1969).
M. H. Altaf, N. H. Badrun, Thermal Hydraulic Analysis of 3 MW TRIGA Research Reactor of Bangladesh Considering Different Cycles of Burnup, Atom Indonesia 40 (2014) 107–112.
Downloads
Published
How to Cite
Issue
Section
License
Authors who publish with CIP agree with the following terms:- The manuscript is not under consideration for publication elsewhere. When a manuscript is accepted for publication, the author agrees to automatic transfer of the copyright to the editorial office.
- The manuscript should not be published elsewhere in any language without the consent of the copyright holders. Authors have the right to enter into separate, additional contractual arrangements for the non-exclusive distribution of the journal’s published version of their work (e.g., post it to an institutional repository or publish it in a book), with an acknowledgement of its initial publication in this journal.
- Authors are encouraged to post their work online (e.g., in institutional repositories or on their websites) prior to or during the submission process, as it can lead to productive exchanges or/and greater number of citation to the to-be-published work (See The Effect of Open Access).
Accepted 05-02-2025
Published 07-03-2025