Last edited by Kigajora
Monday, July 13, 2020 | History

2 edition of Prediction of Fission Gas Release From High Burnup Oxide Fuel. found in the catalog.

Prediction of Fission Gas Release From High Burnup Oxide Fuel.

Atomic Energy of Canada Limited.

Prediction of Fission Gas Release From High Burnup Oxide Fuel.

by Atomic Energy of Canada Limited.

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  • 33 Currently reading

Published by s.n in S.l .
Written in English


Edition Notes

1

SeriesAtomic Energy of Canada Limited. AECL -- 6682
ContributionsHastings, I., Notley, M.
ID Numbers
Open LibraryOL21970180M

Given the coupling between fuel rod thermal state and fission gas release to the gap, fuel performance codes predictions could deviate non-conservatively. This work is framed within the CSN-CIEMAT agreement on “Thermo-Mechanical Behaviour of the Nuclear Fuel at High Burnup”. References 1 R. Manzel, R. P. Bodmer, and G. Bart Fission Gas Release of High Burnup Fuel IAEA Technical Committee Meeting on Fission Gas Release and Fuel Rod Chemistry Related to Extended Burnup Pembroke, Canada 29 April - 1 May IAEA TECDOC () 67 2 F. U. Schlemmer, and G. J. Schlosser Development of thermal Plutonium.

e) fission gas release, and f) fuel rod gas pressure. FRAPTRAN is programmed for use on Windows-based computers but the source code may be compiled on any other computer with a Fortran compiler. Burnup-dependent parameters may be initialized from the FRAPCON-3 steady-state single rod fuel performance code. Fission gas release onset • Irradiation of fresh and high burnup fuel (segments from LWRs) • lnstrumentation: fuel thermocouple - rod pressure sensor • Stepwise power / temp. increase to establish onset of fission gas release • Simultaneous measurement of fuel temperature (most important parameter) and pressure Temperature history and File Size: 1MB.

2), mixed oxide fuel ((U,Pu)O 2), urania-gadolinia (UO 2-Gd 2O 3), and UO 2 with zirconium diboride (ZrB 2) coatings. The cladding types that have been validated are Zircaloy-2, Zircaloy-4, M5, ZIRLO, and Optimized ZIRLO. FRAPCON can predict fuel and cladding temperature, rod internal pressure, fission gas release, cladding axial and hoop. gives that the first fission gas release amount around 8% comes from the rim region of the fuel. This is mainly due to the radial power peaking at the rim of high burnup fuel giving high initial temperature in the rim region. Right after the power pulse, additional fission gas from the center fuel region is released.


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Prediction of Fission Gas Release From High Burnup Oxide Fuel by Atomic Energy of Canada Limited. Download PDF EPUB FB2

C.C. Dollins, M. Jursich / Fission gas release from oxide fuels Tm ''C PRESENT MODEL 10 15 20 25 BURNUP (X 10"20 F/CM3) 30 35 Fig. Comparison between the model predictions and Zinunerman's data with end of life mean temperature of 15 20 25 BURNUP (X lO-^F/CM3) Fig.

by: 3. Spino and Peerani have indicated that at high burn-up there may be a change in stoichiometry of UO 2: ‘Although slight, the expected oxidation of the fuel at very high burn-up, with possible final O/M ratios ranging between and may cause a measurable increase of the diffusivity of species (e.g., U, Xe) in the matrix, and a tangible increase of the fission gas release fraction’.Cited by: During the experiments with 50 MWd/kg U PWR fuel rods (HBO test series; an acronym for high burnup fuels irradiated in Ohi unit 1 reactor), significant cladding failure occurred.

The energy deposition level at the instant of the fuel failure in the test is 60 cal/g fuel, and is considerably lower than those expected and by: Fission gas release (FGR) behavior under rapid heating conditions of high burnup UO2 fuels with developed rim structure has been examined using two different out-of-pile heating techniques with no.

It is concluded that fission gas had been released from the high burn-up structure in three PWR fuel sections with burn-ups ofand GWd/tU. However, a mechanistic approach to correlate observed fission gas release with both fuel and accident conditions including fuel burnup, peak rim temperature, pulse half width, and fuel enthalpy.

Analytical criteria for the onset of fuel fragmentation and Burst Fission Gas Release in fuel rods with ballooned claddings are formulated. On that basis, the GRSW-A model integrated with a fuel behaviour code is updated.

After modification, the updated code is successfully applied to simulation of the Halden LOCA test IFAAuthor: G.

Khvostov. of understanding fuel performance in view of using higher enrichment fuel, achieving higher burn-up and for introducing innovative fuel cycles. He announced that the CEA envisages to hold a series of three such seminars, the present one addressing thermal fuel performance, a second fission gas release and a third concerned with pellet clad.

The performance of today's nuclear fuel, hence UO2, at high burnup is also reviewed with particular emphasis on the recently observed phenomenon of grain subdivision in the cold part of the oxide fuel at high burnup, the so-called "rim" effect.

provide valuable information on fission gas release during power transients at high burn-up as well as clad diametral deformation and fuel swelling as a function of ramp power and hold time. Figure 1 shows the evolution of fission gas release as a function of time during the power ramp for one of the tests using fuel from IFA evaluations of fission gas release data fr om low-power LWR fuel rods at high burnup, the aforementioned release fr action was set to Grain re -structuring is assumed to.

The resulting microstructure, usually referred to as ‘high burnup structure’ or ‘rim zone structure’, is very porous and believed to enhance fission gas release (Jernkvist & Massih, ). From these arguments, it seems likely that the heterogeneity of MOX fuel does enhance fission gas release.

High-Temperature Fuel and Fission Product Behavior in Accident Condition restructuring and low fission gas release. Fission Product Chemistry in Oxide Fuels. Significantly high fission gas release was noticed in the outer fuel pins of all the fuel bundles, with corresponding increase in the internal pressure in the pin.

For the fuel bundle discharged after extended burn up of ab MWd/tU, fission gas release varied from % for the outer pins to less than 1% for the central pin. The large. FISSION GAS RELEASE Design, operation, and FGR data provided by Halden has provided opportunity to compare code predictions to the steady-state FGR from three full-length MOX PWR rods (the ‘mother rods” N06, N12, and P16 for instrumented sections tested in.

Rose, K S.B., and Clough, D J. FISSION GAS RELEASE FROM HIGH BURN-UP CARBIDE FUEL t Kingdom: N. p., Web. @article{osti_, title = {Analysis of transient fission gas behaviour in oxide fuel using BISON and TRANSURANUS}, author = {Barani, T.

and Bruschi, E. and Pizzocri, D. and Pastore, G. and Van Uffelen, P. and Williamson, R. and Luzzi, Lelio}, abstractNote = {The modelling of fission gas behaviour is a crucial aspect of nuclear fuel analysis in view of the related effects on the thermo Author: Barani, T.

prediction of fission gas release • Session II: High burnup issues, code validation on FGR and fuel performance analysis • Session III: Fission gas release measurement and its effect on fuel performance This theme meeting, which exclusively focused on fission gas release in nuclear fuels, was organised in our country for the first time.

IFPE/IFA, Fuel Thermal Behaviour at High Burnup, Halden Reactor: nea IFPE/IFAREV1, fission gas release as a function of burnup at high power ( MWd/kg) nea IFPE/IFA, Fission Gas Release, Power Ramps, High Burnup Fuel: nea IFPE/IFA, Pellet Surface Roughness Effect on Thermal Performances and PCMI: nea @article{osti_, title = {Analysis and modeling of fission product release from various uranium-aluminum plate-type reactor fuels}, author = {Taleyarkhan, R.P.}, abstractNote = {This articles provides a perspective overview and analysis of volatile of fission-product release data obtained for uranium-aluminum (U-Al) reactor fuels, U-Al[sub x] (alloy and dispersed), U[sub 3]O[sub 8]-Al.

The FASTGRASS predictions of fission-gas release vs. burn-up for various grain sizes with an average irradiation temperature and temperature gradient of K and K/cm, respectively. 39 The FASTGRASS predictions of fission-gas release vs.

fuel tem-perature for various grain sizes with a fuel burn-up and averageCited by: 4.Fuel requirements. In once-through nuclear fuel cycles such as are currently in use in much of the world, used fuel elements are disposed of whole as high level nuclear waste, and the remaining uranium and plutonium content is lost.

Higher burnup allows more of the fissile U and of the plutonium bred from the U to be utilised, reducing the uranium requirements of the fuel cycle.The swelling curve of the material exhibits a distinct knee that shifts to higher fission density with increased fission rate due to higher enrichments.

Current state-of-the-art models of fission-gas behavior do not predict such a dependence. Grain “subdivision” has been observed in high-burnup uranium by: 4.