The 12th International Conference on Environmental ... - Events

Session 16-17 Abstracts
6) PROPOSALS ON MANAGEMENT OF AMB SNF - 16169
Nekhozhin Mikhail, FSUE FCNRS, Moscow,Russia
A.V. Yescherkin, V.A. Zotov, S,V. Kazakov, M.A. Nekhozhin, V.P. Smirnov, FSUE FCNRS (Russia);
D.A. Goncharov, OOO NPF Sosny, Dmitrovgrad; E.G. Kudryavtsev, A.V. Khapyorskaya,
Rosatom; Kovacz Y., Hamvas, I., NPS Paks, (Hungary)
AMB SFAs have been storing more than 50 years in cassettes in cooling ponds BV-1 and BV-2 of BNPS Phase 1. Cassettes
are defined as chromium or carbon steel tubes in bundles containing 17 and 35 pieces. At the present time, the condition of these
ponds cannot guarantee safe operation in all modes of SNF storage and management. Accident risk depends, on the one hand, on
expired service life of pond cladding, on the other hand, by unsatisfactory state of SFA and carbon steel cassettes in which spent
fuel assemblies are stored.
<strong>The</strong> previously adopted technology of management of AMB SFA envisaged construction of a dry storage facility in Zheleznogorsk
on the basis of the existing RBMK storage facility, delivery of cassettes with AMB SFA there and a long-term storage. This
technology has a number of significant drawbacks such as:
• complicated development of a safe method of cassette transportation relative to justification of nuclear and radiation safety
as well as limits on hydrogen build-up;
• taking into account that AMB SFAs are 14 m long, dimensions of the facility would increase drastically;
• the problem of nuclear and radiation safety as well as accumulation of hydrogen in storage is not easier than that in transportation;
• technology does not provide a final solution of AMB SFA management;
• AMB fuel contains chemically active ingredients; so it is desirable to make them safer, for example, by fuel processing.
7) AN OVERVIEW ON THE NATIONAL RADWASTES MANAGEMENT STRATEGY
INTO THE CONTEXT OF THE NUCLEAR PROGRAM DEVELOPMENT - 16356
Maria RADU, CENTER OF TECHNOLOGY AND ENGINEERING FOR NUCLEAR OBJECTIVES (CITON),
MAGURELE, ILFOV,Romania, Adrian PANAIT, CENTER OF TECHNOLOGY AND ENGINEERING FOR NUCLEAR
OBJECTIVES (CITON), Magurele,,Romania, Gheorghe Negut, National Agency for Radioactive Waste (ANDRAD)
ROMANIA, MIVENI, ARGES,Romania, Cristian Litescu, National Agency for Nuclear Waste (ANDRAD) Romania,
MIOVENI, ARGES,Romania
At present the main radwaste generator is Cernavoda NPP with 2 x 700 MW units in operation. For the year 2016, the Plant is
predicted to have 4 units in operation.
<strong>The</strong> National Strategy for radioactive waste management was drafted by National Agency for Radioactive Waste (ANDRAD),
the jurisdictional authority for coordinating spent nuclear fuel and radioactive waste management in Romania.
Last year, the Government of Romania established that a new nuclear power plant would be build, so, with this future operational
NPP, the quantity of waste will increase from the today evaluations.
<strong>The</strong>refore the national strategy for radioactive waste management should be reviewed accordingly.
<strong>The</strong> paper presents some preliminary results obtained upon the R&D Programs related to the radioactive waste disposal facilities.
SESSION 17 - HLW CHARACTERIZATION / RECENT ADVANCES IN HLW TREATMENT SYSTEMS
1) SEPARATION OF FISSION PRODUCTS AND ACTINIDES FROM SAVANNAH
RIVER SITE HIGH-LEVEL NUCLEAR WASTES - 16174
David T. Hobbs, Thomas B. Peters, Michael R. Poirier, Fernando F. Fondeur, Charles A. Nash, Samuel D. Fink,
Savannah River National Laboratory, Aiken, SC,United States
Separation methods for the pretreatment of the liquid fraction of high-level nuclear waste (HLW) at the Savannah River Site
(SRS) include solvent extraction for the separation of cesium and adsorption/ion exchange for the removal of strontium and alphaemitting
actinides. <strong>The</strong> solvent extraction process, referred to as Caustic Side Solvent Extraction or CSSX, uses a calixarene extractant
in combination with phase modifiers in a hydrocarbon diluent. Monosodium titanate (MST), a hydrous metal oxide, is the baseline
material for the removal of strontium and alpha-emitting radionuclides (principally 238Pu, 239Pu, 240Pu and 237Np). Two
pretreatment facilities, the Modular Caustic Side Solvent Extraction Unit (MCU) and the Actinide Removal Process (ARP) facility
began radioactive operations at SRS in 2008. Together these facilities can treat approximately 4 million liters of waste per year.
<strong>The</strong> same separation processes are also planned for the much larger Salt Waste Processing Facility (SWPF). <strong>The</strong> SWPF, which has
a design throughput of about 27 million liters per year, is scheduled to begin radioactive operations in 2013.
This paper presents an overview of the separation processes as well as recent research and development activities aimed at
improving separation performance in the pretreatment facilities.
2) SAFETY ASSESSMENT OF GEOLOGICAL DISPOSAL OF HIGH-LEVEL RADIOACTIVE
WASTE IN BOOM CLAY: RELATION WITH THE RADIONUCLIDE INVENTORY - 16418
Pierre Van Iseghem, SCK.CEN, Mol,Belgium
This paper discusses the impact of the parameter values used for the transport of radionuclides from the radioactive waste to
the far-field on the Safety Assessment study for the proposed geological disposal in a Boom Clay formation in Belgium. <strong>The</strong>
methodology of the Safety Assessment is explained, and the results of the Safety Assessment for vitrified high-level waste and spent
fuel are presented. <strong>The</strong> radionuclides having the strongest impact on the dose-to-man for both HLW glass and spent fuel are 79Se,
129I, 126Sn, 36Cl, and 99Tc. Some of them are volatile, and for many of them there is no accurate information on their inventory
in the waste form. We therefore recommend to spend attention to obtain a more accurate inventory of these critical radionuclides
in the HLW forms. <strong>The</strong> hypotheses in the selection of the main parameter values are further discussed, together with the status of
the R&D on one of the major critical radionuclides (79Se).
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