Calculation, measurement and sensitivity analysis of kinetic parameters of Tehran Research Reactor

Hosseini, Seyed Abolfazl; Vosoughi, Naser; Ghofrani, M.; Gharib, Morteza

doi:10.1016/j.anucene.2010.01.018

Cited by 9 publications

(4 citation statements)

References 11 publications

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“…To calculate and validate kinetic parameters, we have considered the following two steps calculations: First step: kinetic parameters of the TRR are calculated and analyzed according to burn-up or amount of fuel consumption. At this step, we have considered the amount of burn-up for 30 days operation at 5 MW reactor power (Usually timescales TRR is in a 30-day cycle) for LEU and HEU cases, [6,8,9].…”

Section: Methodsmentioning

confidence: 99%

“…Also, we assume the temperature changes from 20 o C to 100 o C and the period of effective fuel consumption (burn-up) has been calculated for the period of one month and in two cases of LEU and HEU [7]. Moreover, the results of this study will be validated by a comparison of the results obtained by v 1 poisoning method, Safety Analysis Report (SAR) [6,8,9].…”

Section: Introductionmentioning

confidence: 99%

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Analysis of the thermal feedback and burn up effects on kinetic parameters in TRR by the Monte Carlo method

Khaleghi

Hassanzadeh

2018

J. Phys. Commun.

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In the safety analysis of nuclear reactors, the knowledge about kinetic parameters is significant. Effective delayed neutron fraction b ( ) eff and prompt neutron life time ℓ ( ) p depend on the time behaviour of the reactor power transient after reactivity insertion. Thus, in this article, the sensitivity analysis of the kinetic parameters to physical parameters such as fuel enrichment, fuel consumption (burn-up) and temperature changes in Tehran Research Reactor (TRR) has been investigated. For this purpose, this research has used MCNPX code for these parameters. According to the results, the amounts of ℓ p parameter for v 1 poisoning method and Safety Analysis Report (SAR) are 47.9 and 45.0 μs, respectively. The obtained results have been compared to SAR. It was found that the relative difference is 6.4% for ℓ p parameter. Moreover, the values of b eff parameter for MCNPX code and SAR are 785.64 and 777.7 pcm, respectively. When compared to the available SAR data, a relative difference of 1.1% was obtained for b eff parameter. In most cases, raising the temperature produces higher values of ℓ p but reduces b eff parameters in both LEU and HEU cases. Also, any increment in burn-up no changes in ℓ p parameter but b eff parameter reduces for both LEU and HEU cases.

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Section: Methodsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Analysis of the thermal feedback and burn up effects on kinetic parameters in TRR by the Monte Carlo method

Khaleghi

Hassanzadeh

2018

J. Phys. Commun.

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“…Zaker [5] and Hosseini et al [6] used WIMSD-5B [7], BORGES [8], and CITVAP [9] codes to evaluate the kinetic parameters. WIMS and BORGES are used to calculate neutron cell crosssections.…”

Section: Cnl Nuclear Reviewmentioning

confidence: 99%

“…The parameters are as defined above in calculating weighted neutron generation time. In a similar manner as Λ, the effective delayed neutron fraction can be calculated by using Equation (6) [24] were used to simulate the core.…”

Section: Effective Delayed Neutron Fractionmentioning

confidence: 99%

Kinetic Parameters Calculation During First Cycle of the Wwer-1000 Reactor Core

2019

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Determination of the effective delayed neutron fraction (βeff) and neutron generation time (Λ), on account of their important role in the reactivity transients analysis, safety, and control of nuclear reactors, is of the great importance in the reactor physics calculations. In this paper, evaluation of the kinetic parameters (effective delayed neutron fraction and prompt neutron lifetime) in PWRs is calculated. Software was developed to automate the procedure of kinetic parameters calculations. We used both a deterministic and a probabilistic method for calculation of the delayed neutron parameters. The results performed well in comparison to the reference.

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Calculation of effective point reactor kinetic parameters combined with the Galerkin finite element method

et al. 2020

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Calculation, measurement and sensitivity analysis of kinetic parameters of Tehran Research Reactor

Cited by 9 publications

References 11 publications

Analysis of the thermal feedback and burn up effects on kinetic parameters in TRR by the Monte Carlo method

Analysis of the thermal feedback and burn up effects on kinetic parameters in TRR by the Monte Carlo method

Kinetic Parameters Calculation During First Cycle of the Wwer-1000 Reactor Core

Calculation of effective point reactor kinetic parameters combined with the Galerkin finite element method

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