The 12th International Conference on Environmental ... - Events
The 12th International Conference on Environmental ... - Events
The 12th International Conference on Environmental ... - Events
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Sessi<strong>on</strong> 16-17 Abstracts<br />
6) PROPOSALS ON MANAGEMENT OF AMB SNF - 16169<br />
Nekhozhin Mikhail, FSUE FCNRS, Moscow,Russia<br />
A.V. Yescherkin, V.A. Zotov, S,V. Kazakov, M.A. Nekhozhin, V.P. Smirnov, FSUE FCNRS (Russia);<br />
D.A. G<strong>on</strong>charov, OOO NPF Sosny, Dmitrovgrad; E.G. Kudryavtsev, A.V. Khapyorskaya,<br />
Rosatom; Kovacz Y., Hamvas, I., NPS Paks, (Hungary)<br />
AMB SFAs have been storing more than 50 years in cassettes in cooling p<strong>on</strong>ds BV-1 and BV-2 of BNPS Phase 1. Cassettes<br />
are defined as chromium or carb<strong>on</strong> steel tubes in bundles c<strong>on</strong>taining 17 and 35 pieces. At the present time, the c<strong>on</strong>diti<strong>on</strong> of these<br />
p<strong>on</strong>ds cannot guarantee safe operati<strong>on</strong> in all modes of SNF storage and management. Accident risk depends, <strong>on</strong> the <strong>on</strong>e hand, <strong>on</strong><br />
expired service life of p<strong>on</strong>d cladding, <strong>on</strong> the other hand, by unsatisfactory state of SFA and carb<strong>on</strong> steel cassettes in which spent<br />
fuel assemblies are stored.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> previously adopted technology of management of AMB SFA envisaged c<strong>on</strong>structi<strong>on</strong> of a dry storage facility in Zheleznogorsk<br />
<strong>on</strong> the basis of the existing RBMK storage facility, delivery of cassettes with AMB SFA there and a l<strong>on</strong>g-term storage. This<br />
technology has a number of significant drawbacks such as:<br />
• complicated development of a safe method of cassette transportati<strong>on</strong> relative to justificati<strong>on</strong> of nuclear and radiati<strong>on</strong> safety<br />
as well as limits <strong>on</strong> hydrogen build-up;<br />
• taking into account that AMB SFAs are 14 m l<strong>on</strong>g, dimensi<strong>on</strong>s of the facility would increase drastically;<br />
• the problem of nuclear and radiati<strong>on</strong> safety as well as accumulati<strong>on</strong> of hydrogen in storage is not easier than that in transportati<strong>on</strong>;<br />
• technology does not provide a final soluti<strong>on</strong> of AMB SFA management;<br />
• AMB fuel c<strong>on</strong>tains chemically active ingredients; so it is desirable to make them safer, for example, by fuel processing.<br />
7) AN OVERVIEW ON THE NATIONAL RADWASTES MANAGEMENT STRATEGY<br />
INTO THE CONTEXT OF THE NUCLEAR PROGRAM DEVELOPMENT - 16356<br />
Maria RADU, CENTER OF TECHNOLOGY AND ENGINEERING FOR NUCLEAR OBJECTIVES (CITON),<br />
MAGURELE, ILFOV,Romania, Adrian PANAIT, CENTER OF TECHNOLOGY AND ENGINEERING FOR NUCLEAR<br />
OBJECTIVES (CITON), Magurele,,Romania, Gheorghe Negut, Nati<strong>on</strong>al Agency for Radioactive Waste (ANDRAD)<br />
ROMANIA, MIVENI, ARGES,Romania, Cristian Litescu, Nati<strong>on</strong>al Agency for Nuclear Waste (ANDRAD) Romania,<br />
MIOVENI, ARGES,Romania<br />
At present the main radwaste generator is Cernavoda NPP with 2 x 700 MW units in operati<strong>on</strong>. For the year 2016, the Plant is<br />
predicted to have 4 units in operati<strong>on</strong>.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> Nati<strong>on</strong>al Strategy for radioactive waste management was drafted by Nati<strong>on</strong>al Agency for Radioactive Waste (ANDRAD),<br />
the jurisdicti<strong>on</strong>al authority for coordinating spent nuclear fuel and radioactive waste management in Romania.<br />
Last year, the Government of Romania established that a new nuclear power plant would be build, so, with this future operati<strong>on</strong>al<br />
NPP, the quantity of waste will increase from the today evaluati<strong>on</strong>s.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g>refore the nati<strong>on</strong>al strategy for radioactive waste management should be reviewed accordingly.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> paper presents some preliminary results obtained up<strong>on</strong> the R&D Programs related to the radioactive waste disposal facilities.<br />
SESSION 17 - HLW CHARACTERIZATION / RECENT ADVANCES IN HLW TREATMENT SYSTEMS<br />
1) SEPARATION OF FISSION PRODUCTS AND ACTINIDES FROM SAVANNAH<br />
RIVER SITE HIGH-LEVEL NUCLEAR WASTES - 16174<br />
David T. Hobbs, Thomas B. Peters, Michael R. Poirier, Fernando F. F<strong>on</strong>deur, Charles A. Nash, Samuel D. Fink,<br />
Savannah River Nati<strong>on</strong>al Laboratory, Aiken, SC,United States<br />
Separati<strong>on</strong> methods for the pretreatment of the liquid fracti<strong>on</strong> of high-level nuclear waste (HLW) at the Savannah River Site<br />
(SRS) include solvent extracti<strong>on</strong> for the separati<strong>on</strong> of cesium and adsorpti<strong>on</strong>/i<strong>on</strong> exchange for the removal of str<strong>on</strong>tium and alphaemitting<br />
actinides. <str<strong>on</strong>g>The</str<strong>on</strong>g> solvent extracti<strong>on</strong> process, referred to as Caustic Side Solvent Extracti<strong>on</strong> or CSSX, uses a calixarene extractant<br />
in combinati<strong>on</strong> with phase modifiers in a hydrocarb<strong>on</strong> diluent. M<strong>on</strong>osodium titanate (MST), a hydrous metal oxide, is the baseline<br />
material for the removal of str<strong>on</strong>tium and alpha-emitting radi<strong>on</strong>uclides (principally 238Pu, 239Pu, 240Pu and 237Np). Two<br />
pretreatment facilities, the Modular Caustic Side Solvent Extracti<strong>on</strong> Unit (MCU) and the Actinide Removal Process (ARP) facility<br />
began radioactive operati<strong>on</strong>s at SRS in 2008. Together these facilities can treat approximately 4 milli<strong>on</strong> liters of waste per year.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> same separati<strong>on</strong> processes are also planned for the much larger Salt Waste Processing Facility (SWPF). <str<strong>on</strong>g>The</str<strong>on</strong>g> SWPF, which has<br />
a design throughput of about 27 milli<strong>on</strong> liters per year, is scheduled to begin radioactive operati<strong>on</strong>s in 2013.<br />
This paper presents an overview of the separati<strong>on</strong> processes as well as recent research and development activities aimed at<br />
improving separati<strong>on</strong> performance in the pretreatment facilities.<br />
2) SAFETY ASSESSMENT OF GEOLOGICAL DISPOSAL OF HIGH-LEVEL RADIOACTIVE<br />
WASTE IN BOOM CLAY: RELATION WITH THE RADIONUCLIDE INVENTORY - 16418<br />
Pierre Van Iseghem, SCK.CEN, Mol,Belgium<br />
This paper discusses the impact of the parameter values used for the transport of radi<strong>on</strong>uclides from the radioactive waste to<br />
the far-field <strong>on</strong> the Safety Assessment study for the proposed geological disposal in a Boom Clay formati<strong>on</strong> in Belgium. <str<strong>on</strong>g>The</str<strong>on</strong>g><br />
methodology of the Safety Assessment is explained, and the results of the Safety Assessment for vitrified high-level waste and spent<br />
fuel are presented. <str<strong>on</strong>g>The</str<strong>on</strong>g> radi<strong>on</strong>uclides having the str<strong>on</strong>gest impact <strong>on</strong> the dose-to-man for both HLW glass and spent fuel are 79Se,<br />
129I, 126Sn, 36Cl, and 99Tc. Some of them are volatile, and for many of them there is no accurate informati<strong>on</strong> <strong>on</strong> their inventory<br />
in the waste form. We therefore recommend to spend attenti<strong>on</strong> to obtain a more accurate inventory of these critical radi<strong>on</strong>uclides<br />
in the HLW forms. <str<strong>on</strong>g>The</str<strong>on</strong>g> hypotheses in the selecti<strong>on</strong> of the main parameter values are further discussed, together with the status of<br />
the R&D <strong>on</strong> <strong>on</strong>e of the major critical radi<strong>on</strong>uclides (79Se).<br />
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