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

Session 10 Abstracts
25) RADIATION PROTECTION EXPERIENCES IN RETRIEVAL OF RADIOACTIVE
WASTE AT PÜSPÖKSZILÁGY REPOSITORY (wP-59054)
László Juhász, National Research Institute for Radiobiology and Radiohygiene; Sándor Kapitány,
István Barnabás, Public Limited Company for Radioactive Waste Management;
Anna Mária Motoc, National Research Institute for Radiobiology and Radiohygiene (Hungary)
The radioactive waste disposal facility at Püspökszilágy is declared for disposal of institutional radioactive waste from smallscale
producers in Hungary run by the Public Limited Company for Radioactive Waste Management (PURAM). The repository was
sited in 1971 and commissioned in 1976. The repository is a typical near-surface facility, composed of concrete vaults and special
disposal units.
Because the original licence did not deal with waste acceptance criteria high activity sources and spent sealed radioactive
sources (SSRS) consisting of long-half life and alpha emitting radionuclides were also disposed of. The results of the safety assessments
clearly indicate that the SSRS could result in high doses to individuals who intrude into the facility after the closure and they
could also lead to high doses following any future disruption of the facility by natural processes. Therefore the PURAM launched
a demonstration program for retrieval and removal these radiation sources.
The main aim of the achievement of the demonstration program was that each step of the recovery technologies could be appropriately
tested before starting the full scale retrieval program. Concerning the high level activities of radiation sources and much
elevated radiation fields the demonstration program had to be concerned from the radiation protection…
SESSION 10 — PANEL: EMERGING ISSUES IN THE MANAGEMENT OF I/ILW (1.16)
ABSTRACTS NOT REQUIRED
SESSION 11 — PANEL: HOW CAN NETWORKS IMPROVE THE IMPLEMENTATION OF ER PROJECTS?
THE IAEA NETWORK ON ENVIRONMENTAL MANAGEMENT AND REMEDIATION-ENVIRONET (4.15)
ABSTRACTS NOT REQUIRED
SESSION 12 — WASTE MINIMIZATION, AVOIDANCE, AND RECYCLING (1.3)
1) WASTE MINIMIZATION BY MELTING - RECYCLING OF RADIOACTIVE METALS (wP-59040)
Thomas Kluth, Ulrich Quade, Siempelkamp Nukleartechnik GmbH (Germany)
Preserving resources is the fundamental principle for recycling of waste metals, using it as raw material for new products.
Recycling radioactive metal waste from operational and decommissioned nuclear facilities meets this principle and minimizes the
volume of radioactive waste and consequently saves costs.
For 20 years now, the operation of the melting plant CARLA (Centrale Anlage zum Recyclieren Leichtaktiver Abfälle / central
plant for recycling slightly radioactive waste) alongside the production facilities of the Siempelkamp foundry have delivered
this service with plant licensed for handling radioactive material according to § 7 StrlSchV (the German radiation protection ordinance).
The flexible nature of the facilities and products even allow metals that cannot be released after the primary melt, to be
recycled into components used in nuclear industry, e. g. waste containers made of cast iron or heavy concrete. These recycling
routes are unique in the world and were developed by Siempelkamp in the 1980ies and have been expanded continuously since
then.
More than 5,500 waste containers manufactured from Ductile Cast Iron (DCI) in cylindrical or cubic form licensed for the German
ILW waste repository KONRAD have been manufactured with a recycled metal content of between 15 % and 25 %. Waste
metals…
2) WASTE MINIMIZATION BENEFITS OF DISSOLVABLE PROTECTIVE CLOTHING (wP-59003)
Michael Cournoyer, David Wannigman, Robert Dodge, Los Alamos National Laboratory (USA)
Programmatic operations at the Los Alamos National Laboratory Plutonium Facility (TA-55) involve working with various
amounts of plutonium and other highly toxic, alpha-emitting materials. The spread of radiological contamination on surfaces, airborne
contamination, and excursions of contaminants into the operators breathing zone are controlled through the radiological protection
program. A key element of this program is the proper selection of protective clothing. Re-useable, launderable protective
clothing has been the standard for several decades. Over the years, radioactive waste disposal costs have increased and disposal
options have become more limited. This has prompted the development of single-use, dissolvable protective clothing. Single-use,
dissolvable protective clothing is under evaluation as a replacement for launderable woven textile garments at TA-55. We examined
re-useable, launderable and single-use, dissolvable protective clothing, addressed management issues (residual contamination,
cost, environmental footprint, quality assurance), and waste minimization benefits. Replacement of launderable garments with single-use,
dissolvable protective clothing improves the safety configuration of TA-55 by reducing LLW waste generation. Process
improvements of this type contribute to LANLs scientific and technological excellence by increasing the Laboratorys operational
safety.
3) EVALUATION OF EXTERNAL EXPOSURE DURING BUILDING AND OPERATION OF CONCRETE BRIDGES
CONSTRUCTIONS THAT REUSE THE CONDITIONALLY RELEASED STEELS (wP-59120)
Michal Panik, Vladimir Necas, Slovak University of Technology (Slovakia)
This paper presents ongoing results of the project presented at ICEM`10 related to the topics of reusing the conditionally
released materials from decommissioning. The subject of the reuse of conditionally released materials in this case is modeling of
bridge constructions which reuse the conditionally released steel in the form of reinforcement bars for the concrete bridges. A general
approach for the project was presented at ICEM`10. The activities of the project continue in evaluating the individual effective
doses from the external exposure based on reused conditionally released steels separately for public and for professionals (the inter-
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