Effective delayed neutron fraction βeff and neutron generation time Λ are important factors in reactor physics calculation and transient analysis. In first stage of this research, these kinetics parameters have been calculated for two states of Tehran research reactor (TRR), i.e. cold (fuel, clad and coolant temperature 20°C) and hot (fuel, clad and coolant temperature 65, 49 and 44°C, respectively) using MTR_PC code. In second stage, these parameters have been measured with experimental method based on Inhour equation. For cold state, calculated βeff and Λ by MTR_PC are 0.008315 and 30.190 μsec, respectively. Same parameters in hot state are 0.008303 and 33.828 μsec, respectively. The measured βeff and Λ for cold state (reactor power is range of 100–200 Watt) are 0.008088 and 32.001 μsec, respectively. The calculated and measured values are in good agreement. Relative errors are % 2.8 for βeff and % 5.6 for Λ which are smaller than the other reported results.
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17th International Conference on Nuclear Engineering
July 12–16, 2009
Brussels, Belgium
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4355-0
PROCEEDINGS PAPER
Calculation and Measurement of Kinetics Parameters of Tehran Research Reactor
Seyed Abolfazl Hosseini,
Seyed Abolfazl Hosseini
Sharif University of Technology, Tehran, Iran
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Naser Vosoughi,
Naser Vosoughi
Sharif University of Technology, Tehran, Iran
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Mortaza Gharib,
Mortaza Gharib
Tehran Research Reactor, Tehran, Iran
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Mohammad Bagher Ghofrani
Mohammad Bagher Ghofrani
Sharif University of Technology, Tehran, Iran
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Seyed Abolfazl Hosseini
Sharif University of Technology, Tehran, Iran
Naser Vosoughi
Sharif University of Technology, Tehran, Iran
Mortaza Gharib
Tehran Research Reactor, Tehran, Iran
Mohammad Bagher Ghofrani
Sharif University of Technology, Tehran, Iran
Paper No:
ICONE17-75036, pp. 223-228; 6 pages
Published Online:
February 25, 2010
Citation
Hosseini, SA, Vosoughi, N, Gharib, M, & Ghofrani, MB. "Calculation and Measurement of Kinetics Parameters of Tehran Research Reactor." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 5: Fuel Cycle and High and Low Level Waste Management and Decommissioning; Computational Fluid Dynamics (CFD), Neutronics Methods and Coupled Codes; Instrumentation and Control. Brussels, Belgium. July 12–16, 2009. pp. 223-228. ASME. https://doi.org/10.1115/ICONE17-75036
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