ICEM11 Final Program 9.7.11pm_ICEM07 Final Program ... - Events

Abstracts Session 24
in the disposal environment for packages (physical and chemical conditions, temperature variations, groundwater, radiation fields);
(vii) testing and non-destructive monitoring techniques for quality assurance of cementitious materials; (viii) waste acceptance criteria
for waste packages, waste forms and backfills; transport, long term storage and disposal requirements; and finally (ix) modelling
or simulation of long term behaviours of cementations materials used for packaging, waste immobilization and backfilling,…
2) ELUTION BEHAVIOR OF HEAVY METALS FROM CEMENT SOLIDIFIED PRODUCTS
OF INCINERATED ASH WASTE (wP-59102)
Yoshihiro Meguro, Yoshimi Kawato, Takuya Nakayama,Osamu Tomioka,
Motoyuki Mitsuda, Japan Atomic Energy Agency (Japan)
Combustible radioactive wastes generated from the operation of nuclear facilities are incinerated for volume reduction in
Japan. In Japan Atomic Energy Agency (JAEA) the incinerated ash is planned to be solidified using cement and to be buried in the
ground. Incinerated ashes with various compositions and properties are generated because there are facilities of several kinds of
types such as reactors, nuclear fuel cycle facilities, and hot laboratories in JAEA. And also a small amount of heavy metal, which
is hazardous chemical substance for environment, is also included in the incinerated ash.
The authors push forward a study to determine conditions to produce solidified products of the incinerated ash with cement.
Here relationships between solidification conditions and solidification characteristics have been investigated. The solidification
conditions are the ash composition, cement materials, ash filling rate and water/cement ratio, and the solidification characteristics
are including curing rate and expansion behavior. And also characteristics of the solidified product have been studied, these are
compressive strength, elution behavior of radionuclides and the heavy metals from the solidified products, gas generation by radiolysis,
and so on.
In the present paper, our recent results about the elution behavior of the hazardous heavy metals from synthetic solidified…
3)IMMOBILISATION OF RADWASTE IN SYNTHETIC ROCK: AN ALTERNATIVE TO CEMENTATION (w/P-59008)
Bernard Rottner, Onet Technologies (France)
SOGETER is a waste conditioning process for Low Level radwaste (LLW) or Intermediate Level radwaste (ILW) like sludge,
soil, ashes, evaporator concentrate, concrete rubble, asbestos, sand, & Usually such radioactive waste is solidified into a cement
matrix, resulting in a factor 2 to 5 volume increase: 1 m3 of initial raw waste generates 2 to 5 m3 of solidified waste.
Sogeter consists in melting the waste at high temperature, up to 2000 K, and producing a synthetic rock. The main component
of the matrix is the waste itself; therefore 1 m3 of initial raw waste generates only 0.2 to 0.5 m3 of solidified waste.
Compared to cementation, synthetic rock decreases the volume to be disposed of by a factor of 4 to 25.
By mixing different types of waste, or using additives, the composition of the waste is adjusted, so that a fluid melt is obtained
at temperatures less than 2000 K, and so that the final 200 L ingot may be cooled down within 2 days, without shattering or disaggregating.
We tested a wide range of compositions, demonstrating that almost every type of waste may be conditioned with Sogeter.
We designed the industrial facility, based on a very robust and…
SESSION 24 — L/ILW WASTE CHARACTERIZATION, ASSAY, AND TRACKING SYSTEMS - PART 1 OF 2 (1.7)
1) A PROPOSED FIGURE OF MERIT FOR EVALUATING THE PERFORMANCE
OF RADIATION IDENTIFICATION AND DETECTION SYSTEMS (wP-59159)
Ronald Keyser, Timothy Twomey, ORTEC - AMETEK; Michael D. Belbot, Thermo Fisher Scientific;
Neil Andrew Webster, Thermo Fisher Scientific, Radiation Measurement & Security Instruments (USA)
The instruments used to monitor the radioactive content of waste materials, either in container monitors, hand held radiation
detectors, or mobile analysis systems, are constructed of widely different ways with widely varying detector materials and analysis
software. However, within the various groupings (e.g., automatic waste monitors), all instruments are expected to solve the same
problem, that is, to detect and identify any radioactive material present according to the prescribed investigation methods. The best
way to compare the performance of different instruments is with a numerical score or Figure of Merit (FOM). The FOM must quantity
the performance of the instrument with respect to false positives (FP) and false negatives (FN). The minimization of FN for
certain radionuclides (e.g., uranium and plutonium or SNM) is more important than the minimization of FN for non-threat nuclides
(e.g., low NORM). Likewise, the minimization of FP for SNM is also more important than falsely reporting the common NORM
nuclides. The performance depends on the details of the testing, so the analysis conditions must also be included in the statement
of the FOM. A FOM has been developed based on the number of true positives (TP), the number of false important positives (FIP),
the number…
2) CHARACTERIZATION OF LEGACY LOW LEVEL WASTE AT THE SVAFO
FACILITY USING GAMMA NON-DESTRUCTIVE ASSAY AND X-RAY
NON-DESTRUCTIVE EXAMINATION TECHNIQUES (wP-59289)
Stephen Halliwell, VJ Technologies Inc;
Gary Mottershead, VJ Technologies Inc; Fredrik Ekenborg (USA/France/Sweden)
Over 7000 drums containing legacy, low level radioactive waste are stored at four SVAFO facilities on the Studsvik site which
is located near Nyköping, Sweden. The vast majority of the waste drums (>6000) were produced between 1969 and 1979. The
remainder were produced from 1980 onwards.
Characterization of the waste was achieved using a combination of non-destructive techniques via mobile equipment located
in the AU building at the Studsvik site. Each drum was weighed and a dose rate measurement was recorded. Gamma spectroscopy
was used to measure and estimate radionuclide content. Real time xray examination was performed to identify such prohibited
items as free liquids.
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