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> 48-49 Abstracts<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> most comm<strong>on</strong> method of treatment of such waste streams is the solidificati<strong>on</strong> in a solid matrix with additi<strong>on</strong>al inactive<br />
material like cement, polymer etc. In the past good results have been achieved and the high c<strong>on</strong>centrati<strong>on</strong> of radioactivity can be<br />
reduced by adding the inactive material. On the other hand, under the envir<strong>on</strong>ment of limited space for interim storage and the<br />
absence of a final repository site, the built-up of additi<strong>on</strong>al volume has to be c<strong>on</strong>sidered as very critical. Moreover, corrosive effects<br />
<strong>on</strong> cemented drums during l<strong>on</strong>g-term interim storage at the surface have raised doubts about the l<strong>on</strong>g-term stability of such waste<br />
products.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> paper will discuss alternative treatment opti<strong>on</strong>s by means of drying and compacti<strong>on</strong> in order to achieve volume reducti<strong>on</strong><br />
and high quality waste products.<br />
8) THE INFLUENCE OF SORPTION PROPERTIES OF THE ADMIXTURE WASTE FORM<br />
ON THE MIGRATION OF RADIONUCLIDE FROM SALIGNY REPOSITORY - 16255<br />
Daniela Dogaru, Nati<strong>on</strong>al Commissi<strong>on</strong> for Nuclear Activities C<strong>on</strong>trol (Romania);<br />
Ortenzia Niculae, Nati<strong>on</strong>al Agency for Radioactive Waste (Romania); Gheorghita Jinescu, Politehnica University of<br />
Bucharest (Romania); Octavian G. Duliu, University of Bucharest (Romania); Gheorghe Dogaru, Nati<strong>on</strong>al Institute of<br />
Reserch & Development for Physics and Nuclear Engineering-Horia Hulubei (Romania)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> paper describes the results obtained in the laboratory investigati<strong>on</strong>s <strong>on</strong> the mechanical and sorpti<strong>on</strong> properties of the<br />
cement-based radioactive waste form c<strong>on</strong>taining two kinds of sludge in different c<strong>on</strong>centrati<strong>on</strong>s. One of them simulates the sludge<br />
obtained by treatment of liquid radioactive effluents using an ani<strong>on</strong>ic polyelectrolyte named PA-type, and the other <strong>on</strong>e simulates<br />
the sludge obtained by dec<strong>on</strong>taminati<strong>on</strong> of c<strong>on</strong>taminated surfaces using a hydrogel named pNaAc- type. <str<strong>on</strong>g>The</str<strong>on</strong>g> influence of the c<strong>on</strong>centrati<strong>on</strong><br />
of sludge <strong>on</strong> the compressive as well as <strong>on</strong> bending strength of the cement-based radioactive waste forms was studied.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> sorpti<strong>on</strong> properties of two radi<strong>on</strong>uclides were studied.<br />
SESSION 49 - L/ILW WASTE ANALYSIS TECHNOLOGIES - PART 3 OF 3<br />
1) RADIOLOGICAL MONITORING SYSTEMS FOR WASTE CHARACTERISATION IN THE ENVIRONMENT OF<br />
OUR DECOMMISSIONING SOLUTIONS - 16013<br />
Marina Sokcic-Kostic, Roland Schultheis, NUKEM Technologies GmbH (Germany)<br />
Decommissi<strong>on</strong>ing and dismantling of nuclear sites is an increasing business in Europe and worldwide. New methods and<br />
instruments are demanded to perform it effectively and ec<strong>on</strong>omically. NUKEM Technologies has accepted this challenge and has<br />
shown that there is a specific soluti<strong>on</strong> for each task.<br />
Nukem m<strong>on</strong>itoring systems include Bridge M<strong>on</strong>itors for incoming radwaste, Sorting M<strong>on</strong>itors to separate low, intermediate<br />
and high level waste, Drum/C<strong>on</strong>tainer M<strong>on</strong>itors mainly for outgoing waste, M<strong>on</strong>itors for Room Clearance Measurements and High<br />
Throughput Free Release Measurement Systems. <str<strong>on</strong>g>The</str<strong>on</strong>g> last m<strong>on</strong>itor was designed for a 100% measurement of soil or building material<br />
with up to 50.000 kg waste throughput per hour.<br />
2) MGAV10: THE LATEST EVOLUTION IN THE MULTI-GROUP ANALYSIS CODE - 16248<br />
Stephen Croft, Andrey Bosko, Canberra Industries Inc. (USA); Ray Gunnink, C<strong>on</strong>sulant (USA);<br />
Sasha Philips, Joe Lam<strong>on</strong>tagne, Canberra Industries Inc. (USA); Markku Koskelo, Canberra Albuquerque Inc. (USA);<br />
Robert McElroy, Canberra Industries Inc. (USA)<br />
At many points in the safe and transparent handling of plut<strong>on</strong>ium materials the relative isotopic compositi<strong>on</strong> of the principle<br />
isotopes needs to be known. Sometimes this informati<strong>on</strong> may be of primary interest - such as in the verificati<strong>on</strong> of safeguard declarati<strong>on</strong>s<br />
or in the c<strong>on</strong>firmati<strong>on</strong> of the reactivity of mixed oxide fuel. At other times, e.g., for radioactive waste characterizati<strong>on</strong>, the<br />
isotopic compositi<strong>on</strong> may be needed to calculate specific thermal power or specific sp<strong>on</strong>taneous fissi<strong>on</strong> rates for the item under<br />
study, which can subsequently be combined with calorimetric and correlated neutr<strong>on</strong> counting measurements, respectively, in order<br />
to make quantitative assessments of the mass of Pu and associated nuclides that are present in an item.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> Multi-Group Analysis code MGA is a highly regarded and widely used computer code for the analysis of high resoluti<strong>on</strong><br />
gamma ray spectra in order to extract the relative isotopic compositi<strong>on</strong> of plut<strong>on</strong>ium for a diversity of items with minimal prior<br />
informati<strong>on</strong>. It has been h<strong>on</strong>ed over many years to give reliable results for a broad range of measurement scenarios comm<strong>on</strong>ly<br />
encountered in the fuel cycle. <str<strong>on</strong>g>The</str<strong>on</strong>g> nuclear industry is not dormant however and the demands <strong>on</strong> such codes c<strong>on</strong>tinue to shift as a<br />
combinati<strong>on</strong> of technology and necessity open up new applicati<strong>on</strong> areas. For example, while MGA had its origins in the analysis<br />
of clean spectra <strong>on</strong> product material principally for nuclear safeguards applicati<strong>on</strong>s taken with germanium detectors having good<br />
low-energy resoluti<strong>on</strong>, it is now widely applied to the characterizati<strong>on</strong> of drummed waste forms and the complex spectra from such<br />
items acquired with much larger volume and poorer resoluti<strong>on</strong> detectors often used in such applicati<strong>on</strong>s for the dual use of quantitative<br />
assay of the many gamma-emitters.<br />
This new domain of operati<strong>on</strong>al experience resulted in the need to enhance MGA to deal with spectra of poor statistical quality<br />
and also to cope with some of the complicati<strong>on</strong>s that arise in the analysis of unusual spectra. Together with some additi<strong>on</strong>al<br />
changes made to incorporate feedback since the release of versi<strong>on</strong> 9.63 (which had minor revisi<strong>on</strong>s denoted by the letters A through<br />
H) of the code this has resulted in the creati<strong>on</strong> of MGA v10.<br />
In this paper we shall outline the main changes to the code explaining why they were c<strong>on</strong>ceived and implemented. We illustrate<br />
what kinds of measurement problems can now be addressed over and above the previous capabilities which have been preserved<br />
and verified by the same set of regressi<strong>on</strong> tests that have been applied to previous generati<strong>on</strong> of the code.<br />
3) USE OF A WASTE TRACKING SYSTEM AS A WASTE MANAGEMENT TOOL - 16302<br />
Karan North, Magnox South Ltd (UK)<br />
As the Magnox Reactor Sites transiti<strong>on</strong>ed from electricity generati<strong>on</strong> into decommissi<strong>on</strong>ing, the quantity, types and generati<strong>on</strong><br />
rate of waste changed. Most of the existing waste management systems were developed to support managing operati<strong>on</strong>al wastes;<br />
not those generated from decommissi<strong>on</strong>ing activities. Safe handling, proper <strong>on</strong>site management and offsite disposal of waste<br />
requires informati<strong>on</strong> tracking in an integrated database that is capable of providing detailed reports.<br />
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