Contribution to leaching studies of high-burnup spent nuclear fuel

American Nuclear Society - 12th International High-Level Radioactive Waste Management Conference 2008

Volumn 2, Issue , 2008, Pages 412-417

  De Pablo, J ^a,b   Casas, I ^a   Gimenez J ^a   Clarens, F ^b   Gonzalez Robles E ^b   Serrano Purroy, D ^c   Glatz, J P ^c   Wegen, D ^c   Christiansen, B ^c   Martinez Esparza, A ^d  

^a UNIVERSITAT POLITÈCNICA DE CATALUNYA   (Spain)

^b FUNDACIÓ CTM CENTRE TECNOLÒGIC   (Spain)

^c JOINT RESEARCH CENTRE   (Italy)

^d Empresa Nacional de Residuos Radiactivos SA   (Spain)

Author keywords

[No Author keywords available]

Indexed keywords

AQUEOUS PHASE; BATCH EXPERIMENTS; GAMMA SPECTROMETRY; HIGH-BURN UP; LEACHING SOLUTION; MEAN PARTICLE SIZE; RELEASE FRACTION; ROUGHNESS FACTOR; SPENT NUCLEAR FUELS; SPHERICAL SHAPE;

ACETONE; ACTINIDES; BATCH REACTORS; CALCIUM; DISSOLUTION; EXPERIMENTS; FISSION PRODUCTS; GROUNDWATER; GROUNDWATER RESOURCES; HYDROGEOLOGY; INDUCTIVELY COUPLED PLASMA; INDUCTIVELY COUPLED PLASMA MASS SPECTROMETRY; INDUSTRIAL WASTE TREATMENT; LEACHING; MASS SPECTROMETERS; NUCLEAR ENERGY; NUCLEAR FUELS; ORE ANALYSIS; RADIOACTIVE WASTES; RADIOACTIVITY; SODIUM; SODIUM CHLORIDE; WASTE MANAGEMENT;

CORE SAMPLES;

EID: 70449106829     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (6)

1. C.T. Walker, D. Staicu, M. Sheindlin, D. Papaioannou, W. Goll, F. Sontheimer. "On the thermal conductivity of UO2 nuclear fuel at a high burn-up of around 100 MWd/kgHM". Journal of Nuclear Materials, 350, 19 (2006).
2. L. Johnson, C. Ferry, C. Poinssot, P. Lovera.. "Spent Fuel radionuclide source-term model for assessing spent fuel performance in geological disposal. Part I: Assessment of the instant release fraction". J. Nuclear Materials 346, 56 (2005).
3. F. Clarens, D. Serrano-Purroy, A. Martínez-Esparza, D. Wegen, E. Gonzalez-Robles, J. de Pablo, I. Casas, B. Christiansen and J.P. Glatz. "RN fractional release of High Burn-Up fuel: effect of HBS and estimation of accessible Grain Boundary". XXXI Materials Research Symposia in Scientific Basis for Nuclear Waste Management. Held on Sheefield, England, September 2007.
4. A. M. Fernández. "Preparación de una agua intersticial sintética bentonítica a diferentes salinidades (Preparation of a synthetic bentonitic interstitial water at different salinities)". CIEMAT DMA/M214213/05, Madrid, 2005.
5. Hanson, Mat. Res. Soc. Symp. Proc. 824, 89, (2004).
6. A. Martínez-Esparza, J.A. Gago, J. Quiñones, E. Iglesias, S. Pérez de Andrés.: "Review of influence of burn-up and irradiation history on spent fuel instant release". Contract number: FI6W-CT-2003-02389) NF-PRO (D1.4.2)".