Escape of fission products from defective fuel rods of light water reactors

Schuster, E.; Garzarolli, F.; Kersting, Alyssa; Neeb, K. H.; Stehle, H.

doi:10.1016/0029-5493(81)90033-9

Cited by 20 publications

(4 citation statements)

References 1 publication

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“…2(a) is consistent with that seen for intact versus defective fuel rods in German pressurized water reactors (PWR) and boiling water reactors (BWR) in Fig. 3, where enhancement factors of $300-1000 are typically seen for oxidized fuel that is in good agreement with the value of n ox in Table 2 [36].…”

Section: Model Parameter Evaluation Based On X-2 Defect Experimentssupporting

confidence: 86%

“…The multi-slit element A3N in experiment FFO-103 represents a 'worst-case' defect irradiated at a relatively high power of 48 kW/m where there is essentially no sheathing barrier so that fuel oxidation is maximized. Element A7A is a typical hydride failure that was previously irradiated in FFO-102-1 and FFO-102-3 and subsequently power-cycled in experiments FFO-110 and FFO-109 (Phase II) at low (14-26 kW/m) and intermediate (22)(23)(24)(25)(26)(27)(28)(29)(30)(31)(32)(33)(34)(35)(36)(37)(38) kW/m) linear powers. Finally, element A7E, which was irradiated in experiment FFO-102-1 and then reirradiated at a very high linear power of $67 kW/m in FFO-102-2 (which is beyond normal commercial operating conditions), represents a severe hydride failure.…”

Section: Model Parameter Evaluation Based On X-2 Defect Experimentsmentioning

confidence: 99%

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A model for predicting coolant activity behaviour for fuel-failure monitoring analysis

Lewis

El-Jaby

Higgs

et al. 2007

Journal of Nuclear Materials

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Section: Model Parameter Evaluation Based On X-2 Defect Experimentssupporting

confidence: 86%

Section: Model Parameter Evaluation Based On X-2 Defect Experimentsmentioning

confidence: 99%

A model for predicting coolant activity behaviour for fuel-failure monitoring analysis

Lewis

El-Jaby

Higgs

et al. 2007

Journal of Nuclear Materials

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“…6) [24]. The exception is for the enhancement factor for FFO-103 (n(t) = 2.5 Â 10 4 ), which is significantly higher.…”

Section: Model Validationmentioning

confidence: 64%

A general model for predicting coolant activity behaviour for fuel-failure monitoring analysis

El-Jaby

Lewis

Thompson

et al. 2010

Journal of Nuclear Materials

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a b s t r a c tA mathematical treatment has been developed to predict the release of volatile fission products from operating defective nuclear fuel elements. The fission product activity in both the fuel-to-sheath gap and primary heat transport system as a function of time can be predicted during all reactor operating conditions, including: startup, steady-state, shutdown, and bundle-shifting manoeuvres. In addition, an improved ability to predict the coolant activity of the 135 Xe isotope in commercial reactors is discussed. A method is also proposed to estimate both the burnup and the amount of tramp uranium deposits incore. The model has been validated against in-reactor experiments conducted with defective fuel elements containing natural and artificial failures at the Chalk River Laboratories. Lastly, the model has been benchmarked against a defective fuel occurrence in a commercial reactor.Crown

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“…Iodine behavior in oxide fuel follows a deposit model in which non-volatile iodine diffuse through the uranium oxide to be deposited at the cladding fuel interface [7]. If the cladding is breached, or during fuel dissolution, iodine can then react with water to form volatile iodine compounds.…”

Section: Iodine Behavior In Ebr-ii Sodium Bonded Fuelmentioning

confidence: 99%

The Fate of Radiogenic Iodine During the Electrochemical Treatment of Spent EBR-II Fuel

Frank¹,

Vaden

Westphal

et al. 2010

MRS Proc.

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Radiogenic iodine is one of the more difficult fission products to capture and immobilize during the reprocessing of spent nuclear fuel. However, for metallic fuels reprocessed by electrometallurgical treatment, it is believed that the majority of fission-product iodine is retained during the various processing steps. Spent fuel from the Experimental Breeder Reactor II (EBR-II) at the Idaho National Laboratory (INL) is being treated by a combination of electrochemical and pyrometallurgical methods to deactivate the bond sodium of the fuel, recover uranium, and immobilize fission products for disposal. This paper discusses the progress of various strategies and experiments to confirm the expected retention of iodine during the electrometallurgical treatment of EBR-II spent fuel. This includes surveys of previous observations and measurements, and the direct measurement of iodine from various process samples. Current measurements are aimed at iodine determination in the bond sodium and plenum regions of the fuel, refined iodine measurements in electrorefiner salt, and the retention of iodine during waste form production.

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Escape of fission products from defective fuel rods of light water reactors

Cited by 20 publications

References 1 publication

A model for predicting coolant activity behaviour for fuel-failure monitoring analysis

A model for predicting coolant activity behaviour for fuel-failure monitoring analysis

A general model for predicting coolant activity behaviour for fuel-failure monitoring analysis

The Fate of Radiogenic Iodine During the Electrochemical Treatment of Spent EBR-II Fuel

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