Posiva

Sarjassa esiintyvät teemat
Eurajoki, Eurajoki kunta, Olkiluoto, Radioactive waste disposal, Safety, Shields Geology, berggrund, kallioperä, kapselit, kärnavfall, loppusijoitus, radioaktiiviset jätteet, radioaktivt avfall, sijoitus, slutförvaring, turvallisuus, turvallisuusanalyysi, ydinjätteet, ydinpolttoaineet, ydinturvallisuus.

Kieli
Suomi, englanti
ISSN

1239-3096


Englanti

TeosOsaVarasto
Solubilities of uranium for TILA-991998, 13
Sorption of plutonium on rocks in groundwaters from Posiva investigation sites1998, 12
Geochemical modelling of groundwater evolution and residence time at the Olkiluoto site1998, 10
Through-diffusion, permeability, channel-flow and in situ results for porosity and migration properties of rock samples by He-gas methods1997, 13
Principles of mechanical excavation1997, 12
FEPs and scenarios : auditing of TVO-92 and TILA-96 against international FEP database1997, 11
Fracture network model of the groundwater flow in the Romuvaara site1996, 26
Matrix diffusion in crystalline rocks : coupling of anion exclusion, surface diffusion and surface complexation1996, 25
Deep groundwater redox reactions in the Palmottu uranium deposit : the role of uranium and iron in these processes1996, 24
Sorption of cesium, radium, protactinium, uranium, neptunium and plutonium on rapakivi granite1996, 23
Helium gas methods for rock characteristics and matrix diffusion1996, 22
Hydrogeochemistry of deep groundwaters of mafic and ultramafic rocks in Finland1996, 21
Sorption of protactinium on rocks in groundwaters from Posiva investigation sites1996, 18
Interim report on safety assessment of spent fuel disposal Tila-961996, 17
The Hyrkkölä native copper mineralization as a natural analogue for copper canisters1996, 15
Design report of the canister for nuclear fuel disposal1996, 13
Assessment of alternative disposal concepts1996, 12
Criticality safety calculations for the nuclear waste disposal canisters1996, 11
Gamma and neutron dose rates on the outer surface of the nuclear waste disposal canisters1996, 10
Safety case for the disposal of spent nuclear fuel at Olkiluoto. Definition of reference and bounding groundwaters, buffer and backfill porewaters2014-04
Radionuclide transport in the repository near-field and far-field2014-02
In situ determination of thermal properties of rocks in crystalline rock drill holes with TERO56 and TERO76 devices2013-06
In situ stress measurement with the new LVDT-cell : method description and verification2012-43
Long-term safety of the maintenance and decommissioning waste of the encapsulation plant2012-37
Inspection of disposal canisters components2012-35
Seismic activity parameters of the Olkiluoto site2012-34
Rock suitability classicication RSC 20122012-24
Layout determining features, their influence zones and respect distances at the Olkiluoto site2012-21
Representing solute transport through the multi-barrier disposal system by simplified concepts2012-20
Backfill design 20122012-15
Effects of bedrock fractures on radionuclide transport near a vertical deposition hole for spent nuclear fuel2011-03
Inspection of bottom and lid welds for disposal canisters2010-04
Biosphere assessment report 20092010-03
Models and data report 20102010-01
Background information for NDT qualification of Finnish disposal canisters of spent fuel2008-07
Radionuclide release and transport : RNT-20082008-06
Microbiology of Olkiluoto groundwater 2004-20062008-02
KBS-3H design description 20072008-01
Impact of corrosion-derived iron on the bentonite buffer within the KBS-3H disposal concept : the Olkiluoto site as case study2007-11
Safety assessment for a KBS-3H spent nuclear fuel repository at Olkiluoto : complementary evaluations of safety report2007-10
Safety assessment for a KBS-3H spent nuclear fuel repository at Olkiluoto : process report2007-09
Origin and implications of dissolved gases in groundwater at Olkiluoto2007-04
Olkiluoto site description 20062007-03
Dissolution of unirradiated UO2 and UO2 doped with 233U in 0.01 M NaCI under anoxic and reducing conditions2006-08