Druck Version: Nagra Nationale Genossenschaft für die Lagerung radioaktiver Abfälle Seite: 77970 Datum & Zeit: 26.05.2012 00:51:05 Sprache: DE

   NTBs 2001 – 2012

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Technischer Bericht NTB 11-01

Vorschläge zur Platzierung der Standortareale für die Oberflächenanlage der geologischen Tiefenlager sowie zu deren Erschliessung
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Technischer Bericht NTB 10-01

Beurteilung der geologischen Unterlagen für die provisorischen Sicherheitsanalysen in SGT Etappe 2 - Klärung der Notwendigkeit ergänzender geologischer Untersuchungen
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Technical Report NTB 09-08

Physico-Chemical Characterisation Data and Sorption Measurements of Cs, Ni, Eu, Th, U, Cl, I and Se on MX-80 Bentonite
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Technical Report NTB 09-07

Comparison of the reference Opalinus Clay and MX-80 bentonite sorption data bases used in the Entsorgungsnachweis with sorption data bases predicted from sorption measurements on illite and montmorillonite
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Technical Report NTB 09-06

The Nagra Research, Development and Demonstration (RD&D) Plan for the Disposal of Radioactive Waste in Switzerland
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Technical Report NTB 09-05

Critical Review of Welding Technology for Canisters for Disposal of Spent Fuel and High Level Waste
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Technical Report NTB 09-04

A Review of the Possible Effects of Hydrogen on Lifetime of Carbon Steel Nuclear Waste Canisters
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Technical Report NTB 09-03

Sorption Data Bases for Generic Swiss Argillaceous Rock Systems
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Technical Report NTB 09-02

A Review of Materials and Corrosion Issues Regarding Canisters for Disposal of Spent Fuel and High-level Waste in Opalinus Clay
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Technical Report NTB 08-12

Corrosion of carbon steel under anaerobic conditions in a repository for SF and HLW in Opalinus Clay
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Technical Report NTB 08-10

Chemical reactivity of alpha-isosaccharinic acid in heterogeneous alkaline systems
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Technical Report NTB 08-07

Effects of post-disposal gas generation in a repository for low- and intermediate-level waste sited in the Opalinus Clay of Northern Switzerland
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Technischer Bericht NTB 08-06

Modellhaftes Inventar für radioaktive Materialien MIRAM 08
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Technischer Bericht NTB 08-05

Vorschlag geologischer Standortgebiete für das SMA- und das HAA-Lager.
Begründung der Abfallzuteilung, der Barrierensysteme und der Anforderungen an die Geologie.
Bericht zur Sicherheit und technischen Machbarkeit
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Technischer Bericht NTB 08-04

Vorschlag geologischer Standortgebiete für das SMA- und das HAA-Lager. Geologische Grundlagen
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Technischer Bericht NTB 08-03

Vorschlag geologischer Standortgebiete für das SMA- und das HAA-Lager.
Darlegung der Anforderungen, des Vorgehens und der Ergebnisse
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Technischer Bericht NTB 08-02

Bericht zum Umgang mit den Empfehlungen in den Gutachten und Stellungnahmen zum Entsorgungsnachweis
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Technischer Bericht NTB 08-01

Entsorgungsprogramm 2008 der Entsorgungspflichtigen
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Technical Report NTB 07-01

Grimsel Test Site
Investigation Phase IV
Borehole Sealing
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Technical Report NTB 05-03

Grimsel Test Site
Investigation Phase VI
Pore Space Geometry Project
Characterisation of Pore Space Geometry by 14C-MMA Impregnation
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Technischer Bericht NTB 05-02

«Geologische Tiefenlagerung der abgebrannten Brennelemente, der hochaktiven und langlebigen mittelaktiven Abfälle
Darstellung und Beurteilung der aus sicherheitstechnisch- geologischer Sicht möglichen Wirtgesteine und Gebiete
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Technical Report NTB 05-01

Grimsel Test Site
Investigation Phase V
HPF-Experiment:
Modelling Report
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Technical Report NTB 04-09

A Report of the Spent Fuel Stability (SFS) Project of the 5th Euratom Framework Program:
Spent Fuel Evolution under Disposal Conditions – Synthesis of Results from the EU Spent Fuel Stability (SFS) Project
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Technical Report NTB 04-08

A report of the Spent Fuel Stability (SFS) Project of the 5th Euratom Framework Program:
Estimates of the Instant Release Fraction for UO2 and MOX Fuel
at t = 0.
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Technical Report NTB 04-07

Matrix Diffusion for Performance Assessment – Experimental Evidence, Modelling Assumptions and Open Issues
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Technical Report NTB 04-06

Effects of Post-disposal Gas Generation in a Repository for Spent Fuel, High-level Waste and Long-lived Intermediate Level Waste Sited in Opalinus Clay
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Technical Report NTB 04-05

Modelling of Tracer Profiles in Pore Water of Argillaceous Rocks in the Benken Borehole: Stable Water Isotopes, Chloride and Chlorine Isotopes
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Technical Report NTB 04-04

Comparison of ORIGEN2.1 with Selected Computer Codes
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Technical Report NTB 04-03

Nuclide Transport and Diffusion for Vein and Fracture Flow
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Technical Report NTB 04-02

Experimental and Modelling Investigations on Na-Illite: Acid-Base Behaviour and the Sorption of Strontium, Nickel, Europium and Uranyl
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Technical Report NTB 04-01

Grimsel Test Site
Investigation Phase V
Modelling the Transport of Solutes and Colloids in a Water-Conducting Shear Zone in the Grimsel Test Site
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Technical Report NTB 03-13

Grimsel Test Site
Investigation Phase V
Effective Field Parameter FEP
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Technical Report NTB 03-12

Sorption Data Bases for Opalinus Clay Influenced
by a High pH Plume
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Technical Report NTB 03-11

Grimsel Test Site
Investigation Phase V
GAM – Gas Migration Experiments in a Heterogeneous Shear
Zone of the Grimsel Test Site
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Technical Report NTB 03-10

Time-dependent Flow and Transport Calculations for Project Opalinus Clay (Entsorgungsnachweis)
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Technical Report NTB 03-09

A Generic Procedure for the Assessment of the Effect of Concrete Admixtures on the Retention Behaviour of Cement for Radionuclides: Concept and Case Studies
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Technical Report NTB 03-08

Cellulose Degradation at Alkaline Conditions: Long-Term Experiments at Elevated Temperatures
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Technical Report NTB 03-07

Diffusion of HTO, 36Cl-, 125I- and 22Na+ in Opalinus Clay: Effect of confining pressure, sample orientation, sample depth and temperature
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Technical Report NTB 03-06

Project Opalinus Clay: Integrated Approach for the Development
of Geochemical Databases Used for Safety Assessment
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Technical Report NTB 03-03

Grimsel Test Site
Investigation Phase V
The CRR Final Project Report Series III: Results of the Supporting Modelling Programme
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Technical Report NTB 03-02

Grimsel Test Site
Investigation Phase V
The CRR Final Project Report Series II: Supporting Laboratory Experiments with Radionuclides and Bentonite Colloids
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Technical Report NTB 03-01

Grimsel Test Site
Investigation Phase V
The CRR final project report series I: Description of the Field Phase – Methodologies and Raw Data
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Technischer Bericht NTB 02-24

SMA/WLB:
Bohrlochversiegelung/-verfüllung
SB4a/s schräg
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Technical Report NTB 02-23

Project Opalinus Clay: FEP Management for Safety Assessment – Demonstration of disposal feasibility for spent fuel, vitrified high-level waste and long-lived intermediate-level waste (Entsorgungsnachweis)
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Technical Report NTB 02-22

Project Opalinus Clay: Radionuclide Concentration Limits in the Cementitious Near-Field of an ILW Repository
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Technical Report NTB 02-21

Glass Dissolution Parameters: Update for Entsorgungsnachweis
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Technical Report NTB 02-20

Cementitious Near-Field Sorption Data Base for Performance Assessment of an ILW Repository in Opalinus Clay
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Technical Report NTB 02-19

Far-Field Sorption Data Bases for Performance Assessment of a High-Level Radioactive Waste Repository in an Undisturbed Opalinus Clay Host Rock
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Technical Report NTB 02-18

Near-Field Sorption Data Bases for Compacted MX-80 Bentonite for Performance Assessment of a High-Level Radioactive Waste Repository in Opalinus Clay Host Rock
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Technical Report NTB 02-17

A Comparison of Apparent Diffusion Coefficients Measured in Compacted Kunigel V1 Bentonite with those Calculated from Batch Sorption Measurements and De (HTO) Data: A Case Study for Cs(I), Ni(II), Sm(III), Am(III), Zr(IV) and Np(V)
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Technical Report NTB 02-16

NAGRA/PSI Chemical Thermodynamic Data Base 01/01
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Technical Report NTB 02-15

Diffusion of Tritiated Water (HTO) and 22Na+-ions through Non-degraded Hardened Cement Pastes – II. Modelling Results
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Technical Report NTB 02-14

Stability and Mobility of Colloids in Opalinus Clay
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Technical Report NTB 02-13

Redox Conditions in the Near Field of a Repository for SF/HLW and ILW in Opalinus Clay
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Technical Report NTB 02-12

Application of the Nagra / PSI TDB 01/01: Solubility of Th, U,
Np and Pu
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Technical Report NTB 02-11

Canister Options for the Disposal of Spent Fuel
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Technical Report NTB 02-10

Project Opalinus Clay
Radionuclide concentration limits in the near-field of a repository for spent fuel and vitrified high-level waste
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Technical Report NTB 02-09

Assessment of Porewater Chemistry in the Betonite Backfill for the Swiss SF/HLW Repository
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Technical Report NTB 02-08

The Uptake of Eu(III) and Th(IV) by Calcite under Hyperalkaline Conditions: The Influence of Gluconic and Isosaccharinic Acid
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Technical Report NTB 02-07

Partitioning of Radionuclides in Swiss Power Reactor Fuels
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Technical Report NTB 02-06

Project Opalinus Clay:
Models, Codes and Data for Safety Assessment
Demonstration of disposal feasibility for spent fuel, vitrified high-level waste and long-lived intermediate-level waste (Entsorgungsnachweis)
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Technical Report NTB 02-05

Project Opalinus Clay
Safety Report
Demonstration of disposal feasibility for spent fuel, vitrified high-level waste and long-lived intermediate-level waste (Entsorgungsnachweis)
(vergriffen)
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Technischer Bericht NTB 02-03

Projekt Opalinuston
Synthese der geowissenschaftlichen Untersuchungsergebnisse – Entsorgungsnachweis für abgebrannte Brennelemente, verglaste hochaktive sowie langlebige mittelaktive Abfälle
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Technischer Bericht NTB 02-02

Projekt Opalinuston
Konzept für die Anlage und den Betrieb eines geologischen Tiefenlagers – Entsorgungsnachweis für abgebrannte Brennelemente, verglaste hochaktive sowie langlebige mittelaktive Abfälle
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Technical Report NTB 01-08

Porewater chemistry in compacted re-saturated MX-80 bentonite:
Physico-chemical characterisation and geochemical modelling
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Technical Report NTB 01-07

Water-extractable Organic Matter from Opalinus Clay: Effect on Sorption and Speciation of Ni(II), Eu(III) and Th(IV)
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Technischer Bericht NTB 01-06

Optimierungsstudie für ausgewählte Abfalltypen aus Medizin, Industrie und Forschung
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Technical Report NTB 01-05

Indications for self-sealing of a cementitious repository for lowand intermediate-level waste
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Technical Report NTB 01-04

Calculations of the Temperature Evolution of a Repository for Spent Fuel, Vitrified High-Level Waste and Intermediate Level Waste in Opalinus Clay
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Technical Report NTB 01-03

Contaminant Transport in Fracture Networks with Heterogeneous Rock Matrices: The PICNIC Code
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Technical Report NTB 01-02

Experimental studies on the inventory of cement-derived colloids in the pore water of a cementitious backfill material
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Technical Report NTB 01-01

Model Radioactive Waste Inventory for Reprocessing Waste and Spent Fuel
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