development of waste acceptance procedures in slovenia
TRANSCRIPT
Development of waste acceptance
procedures in Slovenia
Technical Meeting on Training and Demonstration of Waste
Disposal Technologies within the Framework of the
International Low Level Waste Disposal Network (DISPONET) —
Waste Acceptance Procedures
Soulaines-Dhuys, France, 26–28 June 2012
ARAO – Agency for Radwaste Management Bojan Hertl; [email protected]
Nuclear Facilities in Slovenia
Austria
Italy Croatia
Hungary
RR Triga Mark II
NPP
Uranium Mine Žirovski vrh
LILW storage
IAEA Safety Requirement and Guides for RWM processes
RWM process from the cradle to the grave
(NS-R-2: Safety of Nuclear Power Plants: Operation)
SSR-2/2 Safety of Nuclear Power Plants: Commissioning and Operation (2011) NS-G-2.7: Radiation Protection and Radioactive Waste Management
in the Operation of Nuclear Power Plants
Life cycle of nuclear facilities (waste producer)
(WS-R-2) GSR Part 5: Predisposal Management of Radioactive Waste
WS-G-2.5: Predisposal Management of Low and Intermediate Level Radioactive Waste;
DS448: Predisposal Management of Radioactive Waste from Reactors (2010)
Predisposal processes
(WS-R-1 + WS-R-4) SSR-5: Disposal of Radioactive Waste (2011) DS356: Near Surface Disposal of Radioactive Waste
SSG-14 Geological Disposal Facilities for Radioactive Waste (2011)
Life cycle of disposal facilities (waste operator)
Methodological approach for developing WAC
4
Preparation of the preliminary WAC for disposal in Slovenia has
been done under the following conditions:
1. Repository site selection procedure was under way (a short-
listed site Vrbina, Krško)
2. Design documentation for the repository was in an early
stage
3. An evaluation was reviewed of the total radioactive
inventory expected in Slovenia (the evaluation includes
operational waste from the Krško Nuclear Power Plant
(NEK), decommissioning waste from NEK and TRIGA,
small producers - CSRAO in Brinje)
4. A preliminary analysis of long-term safety has been
prepared
5. Qualitative (analytical) characterization has been made of
radioactive waste disposed at the NEK SRSF (solid
radwaste storage facility) and the preliminary WAC for this
storage facility prepared;
6. A characterization procedure has been partially carried out
for radioactive waste stored at the CSRAO in Brinje, and
necessary WAC have been prepared for acceptance and
storage of this waste
Methodological approach for developing WAC
Waste Streams Studies
Analytical Characterization
Raw Wastes Waste Forms Waste Packages
1. Evaporator Concentrates 2. Spent Ion Resins 3. Spent Filters 4. Compressible Waste 5. Non-compressible Waste 6. Specific Waste
Evaporator Concentrates: Process Scheme
Evaporator Concentrates: Waste Forms/Waste Packages
EBD5
Solidification Supercompaction EBC
EBCD6
EBCT1
EB Waste Stream (vermiculite-cement matrix)
Evaporator Concentrates: Waste Forms/Waste Packages
IDDS
DCH1 DCH1/T2
DC Waste Stream (IDDS)
Final package for disposal (N3 vs. N2 concrete container)
N3 N2
Proposed optimized waste classification system
With respect to the WPS and aligned with the identified waste streams and with a revised waste package system proposed waste classes are:
Class LLW-1 is intended for very low level waste (VLLW) and low level waste (LLW) not subject to clearance but with surface dose rate below 0.5 mSv/h.
Class LLW-2 is intended for all other LLW meeting the 2 mSv/h criteria (surface dose rate, definition of low level waste).
Class ILW-1 is intended for ILW suitable to be transported as an IP-2 package after loading into the disposal container.
Class ILW-2 is intended for other ILW not increasing 200 mSv/h surface dose rate.
Class ILW-S (special waste) is intended for reactor internals with surface dose rates above 200 mSv/h, and for sealed sources with individual or combined high total activity.
Proposed optimized waste classification system
Based on the critical nuclides (Cl-36, Ni-59, Nb-94, Ag-108m, I-129), the
maximum concentration for these nuclides has been derived, except
for Ca-41, by applying:
0.1 % of the total inventory for certain critical nuclides as a maximum total
activity in Class LLW-1 containers and
1 % of the total inventory for certain critical nuclides as a maximum total
activity in Class LLW-2, ILW-1 and ILW-2 containers
For Ca-41 the following will apply:
1 % of the total inventory for Ca-41 as a maximum total activity in Class
LLW-1 containers and
10 % of the total inventory for Ca-41 as a maximum total activity in Class
LLW-2, ILW-1 and ILW-2 containers
No limitations have been derived for the ILW-S waste packages as
container type not yet has been selected.
AGENCIJA ZA RADIOAKTIVNE ODPADKE (ARAO)
Parmova 53, Ljubljana, SLOVENIJA
Tel: +386 1 236 32 00
Fax: +386 1 236 32 30
www.arao.si
Thank you for your attention!
Bojan Hertl
e-mail: [email protected]
tel.: +386 1 236 32 14