Results 261 to 270 of about 203,114 (300)

Phase characterisation of simulated high burn-up UO2 fuel

Journal of Alloys and Compounds, 1998
Abstract To determine the lattice constant variation with burn-up and the oxidation behaviour at high temperatures, simulated UO2-spent fuels with burn-ups up to 200 GWd tM−1 were prepared by cold pressing and sintering and characterised by X-ray diffraction analysis and thermogravimetry.
J Cobos, D Papaioannou, J Spino, M Coquerelle   +3 more
openaire   +1 more source

High burn-up structure of U(Mo) dispersion fuel

Journal of Nuclear Materials, 2016
Abstract The evolution of the high burn-up structure (HBS) in U(Mo) fuel irradiated up to a burn-up of ∼70% 235U or ∼5 × 1021 f/cm3 or ∼120 GWd/tHM is described and compared to the observation made on LWR fuel. Scanning and transmission electron microscopy was performed on several samples having different burn-ups in order to get a better ...
A. Leenaers, W. Van Renterghem, S. Van den Berghe   +2 more
openaire   +1 more source

Determination of the radionuclide composition and burn-up of high-burn-up WWER-1000 fuel by destructive methods

Radiochemistry, 2012
A sample of WWER-1000 spent nuclear fuel (SNF) with the burn-up of approximately 50 GW day (t U)−1 was studied by methods of destructive analysis. Data on the content of isotopes of U, Pu, Am, Cm, Nd, and Cs are given. The methods used are briefly described.
E. R. Petrov, B. A. Bibichev, V. D. Domkin, V. V. Kozharin, N. V. Kurenkov, V. S. Mukhin, Yu. A. Panteleev   +6 more
openaire   +1 more source

Monitoring Burn-Up of Spent Fuel Assemblies by Gamma Spectrometry

IEEE Transactions on Nuclear Science, 2013
High-resolution gamma-spectrometry (HRGS) has been used for monitoring burn-up of VVER-440 spent fuel assemblies. The objective is to support burn-up calculations by an independent experimental method. Measurements were carried out using a collimator tube built into the concrete wall of the service pit in the reactor block at the Paks Nuclear Power ...
C. Tam Nguyen, I. Almasi, Z. Hlavathy, J. Zsigrai, L. Lakosi, P. Nagy, T. Parko, I. Pos   +7 more
openaire   +1 more source

Hertzian indentation of advanced lmfbr fuels with simulated burn-up

Journal of Nuclear Materials, 1982
Hertzian indentation fracture of advanced fast breeder reactor fuel materials [mixed carbonitrides, (U0.8, Pu0.2)C0.8N0.2, and nitrides (U0.8Pu0.2)N was evaluated to yield the fracture surface energy, γ, and the fracture toughness, KIc. Both technological grade fuels and fuels with added fission products to chemically simulate burn-up values of 3 and ...
Hj. Matzke, T. Inoue
openaire   +1 more source

Oxygen potential of high burn-up fast breeder oxide fuel

Journal of Nuclear Materials, 1988
The oxygen potential ΔG(O2) of fast breeder mixed oxide fuel (U0.8Pu0.2)O1.98 irradiated to different burn-ups up to 11 at% has been determined between 900 and 1300 K by measurements of the electromotive force in a galvanic microcell. The oxygen potential increases continuously with burn-up, due to the oxidative nature of fission and due to fission ...
Hj. Matzke, J. Ottaviani, D. Pellottiero, J. Rouault   +3 more
openaire   +1 more source

Fuel Microstructural Analysis of Incubation Burn-Up for Fission Gas Release

Journal of Nuclear Science and Technology, 1986
A study was made on an incubation burn-up for fission gas release using fuel swelling microstructural analysis. Conclusions of the study are: (1) The fuel microstructural analysis successfully determined the incubation burn-up. The analyzed values agreed with those estimated by the Halden empirical gas release model. (2) The incubation burn-up obtained
openaire   +1 more source

Hydrides reorientation investigation of high burn-up PWR fuel cladding

Journal of Nuclear Materials, 2015
Abstract The direction of formation of hydride in fuel cladding tube is a major issue for the assessment of the cladding remaining ductility after service. This behavior is quite well known for fresh material, but few results exist for irradiated material.
Stéphane Valance, Johannes Bertsch
openaire   +1 more source

Detailed characterisations of high burn-up structures in oxide fuels

Journal of Nuclear Materials, 2008
Abstract In this paper, a series of post-irradiation examination results on high burn-up structures (HBS) are summarised for a wide variety of fuels (various programmes on PWR UO2 fuels with different claddings and with or without doping, PWR MOX fuels, FBR fuels, etc.).
J. Noirot, L. Desgranges, J. Lamontagne
openaire   +1 more source

Synthesis of Nanostructured Fuels: Mimicking the High Burn-Up Structure

Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, 2014
During its lifetime in the core of a nuclear reactor, the fuel undergoes significant changes in its physical, chemical and morphological characteristics. In outer regions of the fuel pellets the so called “high burn-up” or “rim” structure may form. In this region UO2 grains, with an original size of about 10 μm in fresh dense fuel, are reorganized into
Vaclav Tyrpekl, Raquel Jovani-Abril, Michael Holzhäuser   +2 more
openaire   +1 more source