Modeling the activity and scaling factor of 129I in the primary coolant and CVCS resin of operating PWR

Hwang, Kiwon; Lee, Kun Jai

doi:10.1016/j.anucene.2005.06.008

Cited by 4 publications

(2 citation statements)

References 17 publications

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“…Due to their high capacity factors, these reactors are used as baseline energy producing units. During full power operation, the primary coolant loops of PWR systems have relatively high levels of radiation doses [3] [4].…”

Section: Introductionmentioning

confidence: 99%

Effect of Kinetic Parameters on I-129 Activity from Fuel to Coolant in PWRs

Nasir¹

2017

WJNST

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Effect of kinetic model parameters on fission product (I-129) activity from fuel to coolant in PWRs has been studied in this work. First a computational model was developed for fission product release into primary coolant using ORIGEN-2 as subroutine. The model is based on set of differential equations of kinetic model which includes fuel-to-gap release model, gap-to-coolant leakage model, and Booths diffusion model. A Matlab based computer program FPAPC (Fission Product Activity in Primary Coolant) was developed. Variations of I-129 activity in Primary Heat Transport System were computed and computed values of i-129 were found in good agreement and deviations were within 2%-3% of already published data values. Finally, the effects of coolant purification rate, diffusion constant and gas escape rate on I-129 activity were studied and results indicated that the coolant purification rate is the most sensitive parameter for fission product activity in primary circuit. For changes of 5% in steps from −10% to +10% in the coolant purification rate constant (β), the activity variation after 200 days of reactor operation was 23.1% for the change.

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Section: Introductionmentioning

confidence: 99%

Effect of Kinetic Parameters on I-129 Activity from Fuel to Coolant in PWRs

Nasir¹

2017

WJNST

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“…Radioactive wastes contain transuranic or fissile nuclides and should be classified according to their radioactivity levels so that they would be properly disposed. The wastes generally include a large amount of long-lived non-gamma emitting "difficult to measure" nuclides such as 129 I and 14 C. Measurement of the quantity of such radioactive nuclide has been carried out by conventional method like the scaling factor technique (SF) 5) . However, before applying the technique, the correlation is needed between 'easy-tomeasure' nuclides which are readily measured nondestructively and 'difficult-to-measure' ones such as pureradioactive nuclide.…”

Section: Introductionmentioning

confidence: 99%

Measurement of (γ, n) Reaction Cross Section for Long-lived β-emitting Radionuclide¹²⁹I by using Bremsstrahlung Photons

Rahman

Kuwabara

Katö

et al. 2008

Journal of Nuclear Science and Technology

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Many long-lived non-gamma emitting radioactive nuclei such as 129 I, 14 C and 93 Zr are produced as wastes from nuclear fuel cycle facilities. They are called "difficult-to-measure" radio nuclei. Among them 129 I is a long-livedemitting isotope with a half-life of 1.57 x 10 7 years. Iodine compounds are mobile in the vadose zone and groundwater and increase a significant long-term risk. Transmutation of 129 I is a challenging issue in nuclear waste management and disposal. If 129 I is transmuted into 128 I (half life; 25 minutes), it can easily be measured by a Ge detector. However, the 129 I( , n) reaction cross section has not been measured so far. In this study we have measured the inclusive 129 I( , n) 128 I cross section by using bremsstrahlung photons. The bremsstrahlung photons were produced from a 30-MeV electron linac. Measured average activation cross section agrees with 12% deviation from the evaluated one in the IAEA photonuclear data library. Gamma and neutron fluxes for the ( , n) and the (n, ) reaction were also calculated by the EGS and the MCNP codes.

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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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Modeling the activity and scaling factor of 129I in the primary coolant and CVCS resin of operating PWR

Cited by 4 publications

References 17 publications

Effect of Kinetic Parameters on I-129 Activity from Fuel to Coolant in PWRs

Effect of Kinetic Parameters on I-129 Activity from Fuel to Coolant in PWRs

Measurement of (γ, n) Reaction Cross Section for Long-lived β-emitting Radionuclide¹²⁹I by using Bremsstrahlung Photons

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

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Modeling the activity and scaling factor of 129I in the primary coolant and CVCS resin of operating PWR

Cited by 4 publications

References 17 publications

Effect of Kinetic Parameters on I-129 Activity from Fuel to Coolant in PWRs

Effect of Kinetic Parameters on I-129 Activity from Fuel to Coolant in PWRs

Measurement of (γ, n) Reaction Cross Section for Long-lived β-emitting Radionuclide129I by using Bremsstrahlung Photons

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

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Product

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Measurement of (γ, n) Reaction Cross Section for Long-lived β-emitting Radionuclide¹²⁹I by using Bremsstrahlung Photons