When

2nd to 6th November 2015
Starting at 09:00 am

Where

Montpellier, France
Pullman hotel

Important dates  

Abstract submission deadline: 05.06.2015
Notification of acceptance: 23.07.2015
Proceeding submission: 23.11.2015

Special price for student and early registration

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Presentation of conference

The Scientific Basis for Nuclear Waste Management symposium (SBNWM) originated at the Materials Research Society meeting in 1978. It is mainly focused on the treatment and disposal of low- and high-level nuclear wastes from commercial power generation and fuel reprocessing. Technologies for interim, short-term, and long-term storage and disposal are of interest, including mature processes as well as new and innovative technologies. Technologies and strategies for minimizing waste volume and long-term burden are also of interest and will be discussed, including partitioning and transmutation.

Both spent fuel final disposal and waste forms development, including glass, ceramic, metallic, and composite will be discussed. Waste form modeling, performance testing, and advanced characterization techniques are also of interest. Other topics will include design and operation of waste immobilization facilities, as well as repository design, requirements, and licensing.

 Scientific Basis for Nuclear Waste Management

This symposium continues annually, with the location alternating between MRS meetings in the United States and international locations in countries that have active nuclear waste management research programs. This year, SBNWM XXXIX will be organized in Montpellier while editions XXXX and XXXXI will be held in Boston and Sydney, respectively.

 Location

Located between the Rhône valley and the Pyrenees, at only 10 minutes from the Mediterranean coast, Montpellier is a millennium city in the heart of the southern wine-producing region. It has become a major commercial, cultural and tourist hub, and offers an exceptional conference place.

 Technical visit

Last day of the conference, on Friday 06.11.2015, will allow participants to attend a tour of the CEA research center of Marcoule. Several facilities will be proposed for visit, including the Atalante facility, ICSM and the InfoDem space dedicated to the cleaning and dismantling technologies.

Call for abstracts

Conference Schedule

7 invited speakers, 7 sessions, 1 poster session, 1 technical visit Download complete program here (Preliminary)

09:00 - 10:30

Welcome address

10:30 - 11:00

Session 1: Migration

Chairs : J. Bruno & Ch. Poinssot

Selenite migration in bentonite and its competition with silicate and pertechnetate. Bykov D.
Retention of SeO32- and MoO42- by Afm phases. Ma B.
Effect of pH on the plutonium migration behavior in compacted bentonite. Hamada R.
Hydration sequence of swelling clays exchanged with mixed alkali/alkali-earth cations. Salles F.
Actinides behavior in the deep LNW disposal in the presence of corrosion products. Vlasova I.

13:00 - 14:30

Lunch Break

14:00 - 16:45

Session 2: Intermediate Level Waste

Chairs : L. Vance & X. Deschanels

Magnesium alloys and graphite wastes encapsulated in cementitious materials: reduction of galvanic corrosion using alkali hydroxide activated blast furnace slag. Chartier D.
Behavior of tritium in irradiated nuclear graphite waste: consequences for inventory, decontamination and operational stage of disposal. Toulhoat N.
Leaching of UNGG graphite: study of 36Cl behaviour. Comte J.
Nuclear decontamination of small and/or complex geometry items using a topping gel concept. Gossard A.
Influence of the yield stress on the evolution of a bubble population in a viscoplastic fluid. Marchal A.
Osmosis: the key process that drives water uptake and swelling of eurobitum bituminized radioactive waste. Hendrix K.
Modelling of a metallic phase coming from nuclear waste after high temperature treatment. Laplace A.
Development of materials for the entrapment of radioactive cesium. Causse J.

16:45 - 17:15

Coffee Break

17:15 - 19:00

Session 3: Corrosion

Chairs : C. Degueldre & L. Claparède

Determination of 14C and other activation/fission products in zircaloy-4 cladding from an irradiated UO2 fuel rod segment. Herm M.
In situ electrochemical behavior of titanium alloyw (T40, T64) vs. radiolytic corrosion under γ and 4He2+ Noirault S.
The corrosion of carbon steel in clay porewater at 85°C under stable conditions: results from in situ experiments and implications for nuclear waste repositories. Schlegel M.
Corrosion considerations related to carbon steel radioactive waste packages exposed to cementitious materials. Kursten B.
Prediction model for stress corrosion cracking of stainless steel container for nuclear waste disposal. Nakayama G.
Corrosion processes and microbial activity of carbon steel in the context of geological repository in clay environment. Necib S.
Corrosion of metallic aluminum in cement matrices. Delpech S.

08:30 - 10:30

Session 4: Fuel

Chairs : K. Spahiu & Ch. Jégou

Review about the effect of He on the microstructure of spent nuclear fuel in a repositoryFerry C.
Repartition of the uranium isotopes within the Belgian UOX spent fuel. Mennecart T.
Effect of temperature on the oxidation processes of Pd-doped UO2 under either hydrogen or argon streams saturated with water vapor. Espriu Gascon A.
Dissolution of Th1-xUxO2 ceramics: impact of the homogeneity of the cationic distribution. Claparède L.
Dissolution of spent nuclear fuel fragments at high alkaline conditions under H2 overpressure. González-Robles Corrales E.
Spent nuclear fuel corrosion studies under Fukushima sea water conditions. Serrano D.
Behavior of spent UO2 TRISO coated particles under repository relevant conditions. Curtius H.

10:30 - 11:00

Coffee Break

11:00 - 12:30

Session 4: Fuel

Chairs : K. Spahiu & Ch. Jégou

The oxidative dissolution of irradiated MOX fuel in aqueous solutions containing H2O2. Jegou C.
Long term structural stability of self-damaged actinides bearing fuels. Dieste Blanco O.
Aqueous leaching of milled high burnup UO2 fuel under hydrogen atmosphere. Puranen A.
Alpha - radiolysis effects on the behavior of spent nuclear fuel under repository conditions characterized by Raman. Cobos Sabate J.
Synthesis and solubility of purified coffinite. Szenknect S.
Evidences and pathways for UO2 spent fuel coffinitization from natural analogue studies. Bruno J.

12:30 - 14:00

Lunch Break

14:00 - 16:00

Session 5: Glass

Chairs : Joe Ryan & Jim Neeway

Challenges and recent advances of vitrification technology for the Hanford Tank Waste Treatment and Immobilization Plant. Matyas J
Consideration of vitrification process in the formulation of nuclear waste glass. Pinet O.
Composition - Structure - Properties relationships of peraluminous glasses. Piovesan V.
Chemical diffusion in borosilicate glass melt. Pablo H.
Understanding the effect of glass composition containing RE oxide waste glass on liquidus temperature. Mohd Fadzil S.
Physico-chemical properties of Chernobyl "lava" as an analogue of aged vitrified HLW. Vlasova I.
Radiation effects on high molybdenum bearing heterogeneous borosilicate waste glasses. Patel K.

16:00 - 16:30

Coffee Break

16:30 - 18:00

Session 5: Glass

Invited speaker

Current state of knowledge on nuclear glass corrosion and remaining challenges. Gin S.
Zeolite seeded experiments provide key parameters for modeling nuclear glass alteration resumption. Fournier M.
Impact of Zn, Mg, Ni and Co on the glass leaching: cumulative or competitive effects? Arena H.
New methods for alpha dose rate profile determination at HLW matrix / water interfaces. Tribet M.
The effect of electron irradiation on the structure of sodium aluminum iron phosphate glasses. Stefanovsky S.

19:30 - 22:00

Poster Session

08:30 - 11:30

Session 2: ILW

Chairs : A. Mesbah & S. Neumeier

Innovative materials designed for solid phase extraction processes applied for decontamination of nuclear liquid wastes.Granjean A.
Immobilisation process for contaminated zeolitic ion exchangers from Fukushima.Pletser D.
Capture of radionuclides in porous metal organic frameworks (MOFs). Volkringer C.
Structural characterization of geopolymers for the safe disposal of the fission products 137Cs and 90Sr
Modifications under electron irradiations of functionalized mesoporous silica for the confinement of iodine and caesium. Deschanels X.

10:00 - 10:30

Coffee Break

10:30 - 11:30

Session 2: ILW

Chairs : A. Mesbah & S. Neumeier

Performance of promising porous materials on the capture of radionuclides. Alby D.
Synthesis of core shell nanoparticles to capture radioactive cesium. Mansas C.
Why should CEM III/C cement be preferred to CEM I cement for cationic exchange resins encapsulation? Lafond E.
Synthesis of calcium mono-uranate particles via an aqueous route. Ding W.

11:30 - 12:30

Session 1: Migration

Chairs : S. Szenknect & S. Schumacher

Demonstration of the existence of favorable hydrogeological/ hydrochemical environments of HLW disposal. Kunimaru T.
Categorisation and geological/ hydrogeological modelling of potential host rock environments in japan. Ota K.
Long term safety of the extended SFR - Methodology and conclusions from the SR-PSU project. Vahlund F.
Application of solubility and transport limited radionuclide release in performance assessment of a spent fuel repository in Boom clay. Yu L.

12:30 - 14:30

Lunch Break

14:30 - 15:30

Session 1: Migration

Chairs : S. Szenknect & S. Schumacher

Assessing the impact of repository construction and operation on the performance of the host rock as a barrier - case study: deep geological repository at Olkiluoto. Hellä P.
A thermodynamic analysis on the swelling stress of Na-Bentonite under various solution conditions. Sato H.
Microstructural features of compacted MX-80 bentonite after 15 years long experiments. Matusewicz M.
Matrix pore water study on Olkiluoto veined gneiss and pegmatic granite from structural perspective. Sammaljärvi J.

15:30 - 17:45

Session 5: Glass

Chairs : J. Matyas & S. Gin

Diffusion of lithium through a mature glass alteration layer? Neeway J.
The effects of temperature in the aqueous corrosion of UK nuclear waste glass. Fagcang H.
Development of performance assessment models for glass dissolution. Goto T.
Towards a mechanistic understanding of UK Magnox waste glasses dissolution: A NMR approach for alteration surface characterization. Guo R.
Alteration layer formed during nuclear glass leaching by water: effects of irradiation on structure and formation mechanisms. Mougnaud S.
Hydration induced morphological evolution at glass-liquid interfaces: a new model of long-term glass corrosion. Ryan J.
Degradation of international simple glass in cracks. Rama Krishna C.

20:00 - 23:00

BANQUET (19:30 departure of the bus from the Pullman hotel to the domaine de Verchant)

09:00 - 10:30

Session 6: Ceramic materials

Chairs : D. Gregg & N. Clavier

Cubic zirconia based materials prepared from spent fuel LWR rod treatment. Raison P.
Wasteforms for waste from advanced reprocessing. Hsieh Y.H.
Optimisation of processing parameters for the consolidation of actinide glass-ceramic wasteforms by hot isostatic pressing. Thornber S.
Progress on a synroc waste treatment plant for intermediate-level liquid waste from reactor production of 99Mo. Gregg D.
Sol-gel preparation of Ce, U and Pu brannerites. Vance L.

10:30 - 11:00

Coffee Break

11:00 - 12:00

Session 6: Ceramic materials

Chairs : D. Gregg & N. Clavier

Synthetic analogues of kosnarite mineral as waste forms for the immobilization of actinides and fission products. Bykov D.
Ba substitution in CsAlSi2O6 pollucite and leaching behaviour of Cs2TiSi6O15
Synthesis and structural characterization of Smx(Ca,Th)1-xPO4 and Smx(Ca,U)1-xPO4 solid solutions. Schlenz H.
Structural peculiarities of aged 238Pu doped REE monazites. Shiryaev A.

12:30 - 14:30

Lunch Break

14:00 - 15:45

BMBF session

Conditioning of long-lived radionuclides in ceramic waste forms – A German joint research project. S. Neumeier, D. Bosbach
Structural and vibrational characterization of (La,Pr)PO4 monazite. A. Hirsch
The crystal structure of the rhabdophane compounds REEPO4.0.667 H2O. A. Mesbah
Structural studies on rhabdophane-monazite phase transition in (La,Eu)PO4. Y. Arinicheva
Pu(III) monazite: synthesis, structure, and characterization. K. Popa
Incorporation of Cm3+ and Eu3+ in LnPO4 ceramics – A site-selective TRLFS study. N. Huittinen
Structural stability study of the mixed La0.7-xLuxEu0.3PO4 solid solutions by Extended X-ray Absorption Spectroscopy. M.J. Lozano-Rodriguez

15:45 - 16:15

Coffee Break

16:45 - 18:00

BMBF session

Ceramic waste forms in nuclear waste management applications: Status and perspective. D. Gregg
Sintering behaviour and microstructure of rare earth phosphates REPO4 (with RE =La, Ce, Pr). C. Schausten
Physical and microstructural properties of monazite-type ceramics. A. Thust
Study of dissolution of monazite: kinetic point of view. C. Gausse
Leaching of plutonium from "old" samples of single-phase ceramics based on (Zr0.79Gd0.14Pu0.07)O1.99 and (La0.9Pu0.1)PO4 doped with 238Pu B. Zubekhina
In-situ structural investigations on monazite-type La0.2Gd0.8PO4 under heavy ion irradiation. S. Neumeier

08:00 - 18:00

Technical visit of CEA research center of Marcoule (transfer by bus)


8:00 Bus departure from the Pullman hotel, Montpellier
Visit of the Atalante facility, vitrification and long-term behavior laboratories & decommissioning exhibition.
18:00 Bus return at the Pullman hotel, Montpellier

Scientific committee

Rod
EWING

Univ.Stanford, USA

Specific conditioning matrices

Stéphane
GIN

CEA Marcoule, France

Nuclear glass

Luc
VAN DEN DURPEL

AREVA, France

Energy scenario

Dirk
BOSBACH

FZ Jülich, Germany

Material dissolution

Jean-Paul
GLATZ

ITU, Karlsruhe, Germany

Spent fuel

Jordi
BRUNO

AMPHOS21, Barcelona, Spain

Performance assessment

Kastriot
SPAHIU

SKB, Stockholm, sweden

Actinides chemistry

Stéphane
BOURG

CEA Marcoule, France

Partitioning technologies

Stéphane
SCHUMACHER

ANDRA, France

Geological repository

Claude
DEGUELDRE

Univ Geneve, Switzerland

Actinide materials

Neil
HYATT

Univ.Sheffield, UK

Intermediate level wastes

Kastriot
SPAHIU

SKB, Stockholm, sweden

Actinides chemistry

Josef
MATYAS

PNNL, USA

Radiological materials & detection

Daniel
GREGG

ANSTO, Australia

Specific conditioning matrices

Nicolas
DACHEUX

Univ. Montpellier, France

Co-chairman

Christophe
POINSSOT

CEA Marcoule, France

Co-chairman

Organizing committee

Nicolas
DACHEUX

Univ. Montpellier, France

Christophe
POINSSOT

CEA Marcoule, France

Julien
CAMBEDOUZOU

ENSCM, France

Nicolas
CLAVIER

CNRS, France

Stéphane
GIN

CEA Marcoule, France

Adel
MESBAH

CNRS, France

Stéphanie
SZENKNECT

CEA Marcoule, France

Mariette
TUFFERY

CEA Marcoule, France

Stefan
NEUMEIER

FZ Julïch

Registration & Fees

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€650

€650

1

Early registration

Save 100€

Before 10-10-2015, Including the attendance to the 4-day conference, all the coffee-breaks and lunches, the poster buffet and the conference dinner.

€420

€420

2

Student Early registration

Save 100€

Before 10-10-2015, Including the attendance to the 4-day conference, all the coffee-breaks and lunches, the poster buffet and the conference dinner.

€70

€70

3

Conference dinner

For accompanying person

Location and Venue

area full of great hotels and restaurants.


The 39th edition of the MRS 2015- Scientific Basic for Nuclear Waste Management symposium will be held at the Pullman hotel “Montpellier-centre”.

Located between the Rhône valley and the Pyrenees, at only 10 minutes from the Mediterranean coast, Montpellier is a millennium city in the heart of the southern wine-producing region. It has become a major commercial, cultural and tourist hub, and offers an exceptional conference place.

Montpellier's international airport has connections to 60 destinations across France, Europe and worldwide. With 11 daily services from Paris aboard France`s famous TGV, the center of Montpellier is only a 3.15 hour train ride away. By road it is a short drive from key cities such as Marseille, (1.30hrs), Barcelona (2.30hrs) and Geneva (4hrs).



Accomodation

We can propose you rooms at the Pullman hotel at negociated rates. The Pullmann hotel is located in the heart of town, 5 min by foot from the historical center of Montpellier (place de la Comédie, Fabre museum) and near the Polygone shopping center.

Pullman Hotel

1, rue des Pertuisanes

34000 Montpellier

Book Online
Access

By car: take exit 29 “Montpellier centre” and then the direction of “centre historique”. Follow the direction of “parking du centre commercial le Polygone” level P4 at first and then level P3 to have direct access to the hotel.

By train: Montpellier St Roch train station is 5 min from the hotel.

By plane: Montpellier-Méditerranée airport by shuttle bus (Navette Aéroport Montpellier, ligne 120) or taxi – 15 min.

By tram: Take the Odysseum tramway (L1) and get off at the Antigone stop.

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