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

Session 19 Abstracts
4) COMPUTATIONAL STUDY FOR INVENTORY ESTIMATION OF SE-79, TC-99, SN-126, AND CS-135 IN HIGH-
LEVEL RADIOACTIVE WASTES FROM SPENT NUCLEAR FUELS OF LIGHT WATER REACTORS (wP-59087)
Keisuke Okumura, Shiho Asai, Yukiko Hanzawa, Tsutomu Okamoto, Hideya Suzuki, Masaaki Toshimitsu,
Jun Inagawa, Takaumi Kimura, Japan Atomic Energy Agency; Satoru Kaneko,
Kensuke Suzuki, Tokyo Electric Power Company (Japan)
Inventory estimation of long-lived fission products (LLFPs) in high-level radioactive wastes (HLW) from spent nuclear fuels
of light water reactors is important for a safety assessment of their disposal. In order to develop an inventory estimation method of
difficult-to-measure LLFPs (Se-79, Tc-99, Sn-126, and Cs-135), a parametric study was carried out by using a sophisticated burnup
calculation code and data. In the parametric study, fuel specifications and irradiation conditions are changed in the conceivable
range. The considered parameters are fuel assembly types (PWR / BWR), U-235 enrichment, moderator temperature, void fraction,
power density, and so on. From the calculated results, we clarify the burnup characteristics of the target LLFPs and their possible
ranges of generations. Finally, candidates of the key nuclide are proposed for the scaling factor method of HLW.
5) INDUSTRIAL SCALE HL-LL WASTE CANISTER TRANSFER DEMONSTRATOR (wP-59305)
Pascal Champ, Jacques Bardet, Benjamin Attias, Cegelec (France)
In 2007, Cegelec has been attributed a contract by ANDRA under the ESDRED program (Engineering Studies and Demonstrations
of Repository Designs) financed by 13 organisations across Europe, for the design, manufacturing and trial test of a full scale
industrial demonstrator of HL-LL waste canister transfer system.
Completed in 2009, this project gives a good synthesis of solutions the industry can offer in order to manage HLW transportation
with regard to deep geological disposal.
This paper highlights solutions developed and results achieved with numerous pictures of the actual system.
6) CESAR5.3: AN INDUSTRIAL TOOL FOR IRRADIATED NUCLEAR FUEL
AND WASTE CHARACTERISATION, WITH AN ASSOCIATED QUALIFICATION (w/oP-59080)
Jean-Marc Vidal, Romain Eschbach, Commissariat à lÉnergie Atomique et aux Énergies Alternatives;
Agnes Launay, Christophe Binet, AREVA_NC (France)
CESAR (Simplified Evolution Code Applied to Reprocessing) is a depletion code developed between CEA and AREVA. This
code was first used in the La Hague reprocessing plant Laboratories in 1980, to confirm the nuclear data experimental measurements.
The use of the CESAR code was then extended to the characterizations of various type of irradiated nuclear fuel (PWR/UOx
URE and MOx ; BWR/UOx and MOx ; MTR and Fast Reactors) and the associated produced waste. The code can distinguish more
than 100 heavy nuclides, 200 fission products and 150 activation products (in particular Tritium and Helium generation are included).
Both the fuel and its structural materials can be characterized. The CESAR code can also perform depletion calculations from
3 months to 1 million years of cooling time.
The updated version of the code is related to the harmonization between nuclear data and calculation schemes (APOLLO2)
based on the JEFF3.1.1 nuclear data library. The current features allow fast characterizations for both irradiated fuel and waste, calculating:
material balance, activity, decay heat, neutron source and spectrum, radiotoxicity source, gamma and alpha source and
their respective spectrum. The CESAR code can also calculate the coefficients used in nuclear material transport and in classification
of…
7) TEST PROCEDURE WITH A 15,000 KG HALF-SCALE PROTOTYPE
OF TRANSPORT AND STORAGE CASK (w/oP-59141)
Andre Musolff, Thomas Quercetti,
Karsten Müller, BAM - Federal Institute for Materials Research and Testing (Germany)
BAM is the competent authority for mechanical and thermal safety assessment of transport packages for spent fuel and high
level waste in Germany. In context with the package design approval procedure for transport and storage of new German cask several
drop test series were performed by BAM with a half-scale prototype.
The test program comprised a sequence of a total of 18 drop tests with different drop orientations, drop heights and temperatures.
The sequence of testing in the program consisted of a number of nine-meter free drop onto an unyielding target and several
drops from one meter onto a steel puncture bar. In order to cause maximum damage on the package various drop orientations were
performed according to the most severe drop position as well as most sensitive parts of the container.
The subsequent release of radioactive substances must not exceed a value specified in the dangerous goods transport regulations.
Radiation shielding and nuclear safety has to be guaranteed. The prototype was tested under normal and accident conditions
of transport in the 200 tons BAM drop test facility at BAM Test Site Technical Safety.
Extensive test methods as well as comprehensive measurement data are presented within the complexity of performed drop test
procedures.
8) CAPILLARY ELECTROPHORESIS WITH LASER-INDUCED FLUORESCENT DETECTION METHOD USING
HIGHLY EMISSIVE PROBES FOR ANALYSIS OF ACTINIDES IN RADIOACTIVE WASTES (wP-59092)
Tomoko Haraga, Japan Atomic Energy Agency; Yuta Nakano, Masami Shibukawa, Saitama University; Yutaka Kameo,
Kuniaki Takahashi, Japan Atomic Energy Agency; Shingo Saito, Saitama University (Japan)
For the safe disposal of radioactive wastes, it is indispensable to evaluate radioactivity concentration in each waste package.
Actinides are important nuclides for the safety analysis of radioactive wastes from nuclear fuel cycle facilities. In order to analyze
many kinds of waste samples, a simple, fast and highly sensitive analytical method for actinides is required. While capillary electrophoresis
(CE) has been employed for the analysis of ionic species including actinide ions with advantage of the high separation
efficiency and simpleness so far, there is no report for CE method providing high sensitivity amenable to practical use, to our
knowledge. In this study, an approach to develop new emissive probes for actinide ions using CE-laser-induced fluorescent detection
(LIF) was made for the first time. The separation and detection of neptunium (Np-237) and americium (Am-243) was exam-
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