Journal of Nuclear Materials

1

Gamma radiolysis of NaCl brine: Effect of dissolved radiolysis gases on the radiolytic yield of long-lived products

M. Kelm, E. Bohnert

Journal:

Year:

2005

Language:

english

File:

PDF, 124 KB

english, 2005

2

The effects of alpha-radiolysis on UO2 dissolution determined from batch experiments with 238Pu-doped UO2

S. Stroes-Gascoyne, F. Garisto, J.S. Betteridge

Journal:

Journal of Nuclear Materials

Year:

2005

Language:

english

File:

PDF, 227 KB

english, 2005

3

The inhibiting effects of hydrogen on the corrosion of uranium dioxide under nuclear waste disposal conditions

M.E. Broczkowski, J.J. Noël, D.W. Shoesmith

Journal:

Journal of Nuclear Materials

Year:

2005

Language:

english

File:

PDF, 312 KB

english, 2005

4

Spent fuel radionuclide source-term model for assessing spent fuel performance in geological disposal. Part I: Assessment of the instant release fraction

Lawrence Johnson, Cécile Ferry, Christophe Poinssot, Patrick Lovera

Journal:

Journal of Nuclear Materials

Year:

2005

Language:

english

File:

PDF, 337 KB

english, 2005

5

Enhanced diffusion under alpha self-irradiation in spent nuclear fuel: Theoretical approaches

Cécile Ferry, Patrick Lovera, Christophe Poinssot, Philippe Garcia

Journal:

Journal of Nuclear Materials

Year:

2005

Language:

english

File:

PDF, 162 KB

english, 2005

6

Leaching behaviour of unirradiated high temperature reactor (HTR) UO2–ThO2 mixed oxides fuel particles

Cyrille Alliot, Bernd Grambow, Catherine Landesman

Journal:

Journal of Nuclear Materials

Year:

2005

Language:

english

File:

PDF, 328 KB

english, 2005

7

Radiolytic modelling of spent fuel oxidative dissolution mechanism. Calibration against UO2 dynamic leaching experiments

J. Merino, E. Cera, J. Bruno, J. Quiñones, I. Casas, F. Clarens, J. Giménez, J. de Pablo, M. Rovira, A. Martínez-Esparza

Journal:

Journal of Nuclear Materials

Year:

2005

Language:

english

File:

PDF, 168 KB

english, 2005

8

Radionuclide release from high burnup spent fuel during corrosion in salt brine in the presence of hydrogen overpressure

Andreas Loida, Volker Metz, Bernhard Kienzler, Horst Geckeis

Journal:

Journal of Nuclear Materials

Year:

2005

Language:

english

File:

PDF, 320 KB

english, 2005

9

Spent fuel radionuclide source term model for assessing spent fuel performance in geological disposal. Part II: Matrix alteration model and global performance

Christophe Poinssot, Cécile Ferry, Patrick Lovera, Christophe Jegou, Jean-Marie Gras

Journal:

Journal of Nuclear Materials

Year:

2005

Language:

english

File:

PDF, 259 KB

english, 2005

10

Preface

Christophe Poinssot, Robert Finch

Journal:

Journal of Nuclear Materials

Year:

2005

Language:

english

File:

PDF, 57 KB

english, 2005

11

Editorial board

Journal:

Journal of Nuclear Materials

Year:

2005

File:

PDF, 15 KB

2005

12

Conference Title Page

Journal:

Journal of Nuclear Materials

Year:

2005

File:

PDF, 27 KB

2005

13

Manuscript receipt date

Journal:

Journal of Nuclear Materials

Year:

2005

File:

PDF, 7 KB

2005

14

Volume 346; Issue 1

Gamma radiolysis of NaCl brine: Effect of dissolved radiolysis gases on the radiolytic yield of long-lived products

The effects of alpha-radiolysis on UO2 dissolution determined from batch experiments with 238Pu-doped UO2

The inhibiting effects of hydrogen on the corrosion of uranium dioxide under nuclear waste disposal conditions

Spent fuel radionuclide source-term model for assessing spent fuel performance in geological disposal. Part I: Assessment of the instant release fraction

Enhanced diffusion under alpha self-irradiation in spent nuclear fuel: Theoretical approaches

Leaching behaviour of unirradiated high temperature reactor (HTR) UO2–ThO2 mixed oxides fuel particles

Radiolytic modelling of spent fuel oxidative dissolution mechanism. Calibration against UO2 dynamic leaching experiments

Radionuclide release from high burnup spent fuel during corrosion in salt brine in the presence of hydrogen overpressure

Spent fuel radionuclide source term model for assessing spent fuel performance in geological disposal. Part II: Matrix alteration model and global performance

Preface

Editorial board

Conference Title Page

Manuscript receipt date

Contents