Modelling the activity of 129I in the primary coolant of a CANDU reactor

Lewis, Brent J.; Husain, Akbar

doi:10.1016/s0022-3115(02)01588-x

Cited by 27 publications

(49 citation statements)

References 22 publications

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“…Specific activity of fission products in the fuel-to-clad gap and further in the reactor coolant depends on many factors, such as the number of defective fuel elements, reactor power history, fuel burnup, and the reactor coolant purification system [4,8].…”

Section: Rbmk-1500 Reactor Specificsmentioning

confidence: 99%

“…Another temperature-independent process of release is knockout, when either a primary fragment or energetic particle created in a collision cascade interacts elastically with a fission product atom. The FP recoil and knockout from fuel pellets do not significantly contribute to the gap inventory [4], the actual contribution to the total FP release is less than 1% of the generated gas [15,16]. However, due to lower temperatures of fuel debris, only direct recoil is an important mechanism of release into the MCC coolant from uranium contamination deposited on in-core surfaces [4].…”

Section: Fission Product Release From Defective Fuel Elementsmentioning

confidence: 99%

“…FP of a particular group will behave similarly. Moreover, isotopes of any element will be defined by characteristic migration parameters, e. g., all isotopes of iodine can be characterised by the diffusion coefficient, release rate from defective fuel, and the clean-up rate in ion exchange resins [4]. Therefore, measurement of some easy-to-measure radionuclides can give us information on the migration properties and furthermore, activities of DTMR in the reactor MCC coolant.…”

Section: Introductionmentioning

confidence: 99%

“…The purpose of this work is to evaluate the release of iodine isotopes from the RBMK-1500 reactor fuel-to-clad gap to the MCC coolant. A model for the CANDU reactor primary circulation circuit [4] is adapted for the RBMK-1500 case taking into account all activity measurement and reactor specifics outlined in the following sections.…”

Section: Introductionmentioning

confidence: 99%

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Analysis of iodine release from the defective fuel elements of the RBMK-1500 reactor

Klevinskas¹

2007

Lithuanian J. Phys.

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The results of modelling and analysis of iodine release to the main circulation circuit of the RBMK-1500 reactor are presented. General approach proposed by Lewis and Husain for the CANDU reactor primary coolant activity prediction was applied. Specific features of the RBMK-1500 coolant activity measurement were assessed. Non-stationary activity measurement conditions were identified and quantified with corresponding correction factors. Parameter values of the adapted model are comparable with those characteristic of CANDU reactor defective fuel.

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Section: Rbmk-1500 Reactor Specificsmentioning

confidence: 99%

Section: Fission Product Release From Defective Fuel Elementsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Analysis of iodine release from the defective fuel elements of the RBMK-1500 reactor

Klevinskas¹

2007

Lithuanian J. Phys.

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“…Fission products are also additionally generated during the fission of "tramp" uranium, whose particles are deposited on the outside of the fuel components' claddings (contaminated during manufacturing of the fuel). During operation the coolant could be contaminated with these particles too [7]. Spectrum of the fission products of the "tramp" uranium is analogous to the spectrum of fission products in nuclear fuel.…”

Section: Introductionmentioning

confidence: 99%

Modelling of the Radiological Contamination of the RBMK-1500 Reactor Control and Protection System Channels’ Cooling Circuit

Poskas¹,

Zujus²

2015

WJET

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The article presents results of modelling and analysis of component contamination of the RBMK-1500 reactor Control and Protection System channels' Cooling Circuit (CPSCC) at Ignalina NPP Unit 1. The modelling was performed using a computer code LLWAA-DECOM (Tractebel Energy Engineering, Belgium), taking into consideration CPSCC components characteristics, parameters of the water flowing in the circuits, system work regimes, etc. During the modelling, results on activity of CPSCC components' deposits, nuclide composition of the deposits and dose rates after the final shutdown of the reactor, as well as activity decay of the most contaminated CPSCC components' deposits were obtained. Analysis showed that there is a significant difference in contamination levels between CPSCC components. The rundown header from the channels of the reactor's fast acting scram system is the most contaminated component, and contamination of the least contaminated component is only 0.27% compared to the activity of the most contaminated component. Corrosion nuclides are the nuclides that mostly contribute to contamination of the CPSCC deposits.

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Impact of operational changes on the scaling factors of radioactive wastes from the IEA-R1 research reactor

Taddei

Macacini

Vicente

et al. 2016

J Radioanal Nucl Chem

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Modelling the activity of 129I in the primary coolant of a CANDU reactor

Cited by 27 publications

References 22 publications

Analysis of iodine release from the defective fuel elements of the RBMK-1500 reactor

Analysis of iodine release from the defective fuel elements of the RBMK-1500 reactor

Modelling of the Radiological Contamination of the RBMK-1500 Reactor Control and Protection System Channels’ Cooling Circuit

Impact of operational changes on the scaling factors of radioactive wastes from the IEA-R1 research reactor

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