The 12th International Conference on Environmental ... - Events

Abstracts Session 45
testing and optimization phases of the particle detection system which was created to simulate an overland survey environment as
realistically as possible. MACTEC was able to successfully demonstrate the capabilities of the system by not only meeting the identified
specifications, but by beating the clients specifications while saving significant costs that would be incurred with a full-scale
test deployment methodology.
C) INDEPENDENT MONITORING OF RADIOLOGICAL IMPACT AT DECOMMISSIONED NPP A1 SITE - 16074
Ondrej Slavik, Martin Listjak, Alojz Slaninka, Jozef Moravek (SlovaKia); Frantisek Soos, JAVYS, a.s. (Slovakia); Sylvia
Dulanska, Comenius University (Slovakia)
Monitoring of characteristics of the radiation situation in close surrounding of the decommissioned NPP A1 by an independent
organization is described and discussed in the paper. <strong>The</strong> measurements are carried out in the NPP A1 site close to the VUJE
operation building, not far from the places, where the decommissioning activities are concentrated. <strong>The</strong>se activities relate to bringing
the NPP A1 to safer conditions, e.g. cleanup of contaminated underground waste water reservoirs, solidification of the removed
sludge from these reservoirs by an in situ open air solidification system, cleaning of contaminated concretes and so on. Other activities
also relate to radiological impact to the environment, e.g. radioactive waste processing at Bohunice RW-Treatment Centre and
intensive traffic of sources of ionising radiation to and from this centre located very close to the place mentioned above. Results of
the measurements carried out by VUJE accredited laboratory in the frame of Decommissioning project of NPP A1 present an uninterrupted
time series of measurements and enable evaluation of development for the last 17 years. <strong>The</strong> monitoring results demonstrate
that the only significant radionuclide indicating radiological impact of the decommissioning is 137Cs. Its activity concentration
in atmospheric aerosols at the sampling point has been time to time elevated and in average is by about one order higher in
comparison with a 100 km far reference (background) site.
D) EXPERIENCE OF THE INTERNATIONAL COOPERATION UNDER THE RUSSIAN-AMERICAN
AGREEMENT ON REPATRIATION HEU SNF OF RESEARCH REACTORS (EXPORT FROM
BULGARIA, LATVIA, HUNGARY, ETC. THE COUNTRIES) - 16172
Borovitskiy Stepan, FSUE FCNRS (Russia)
Keystone of the Russian Federation policy concerning the SNF management is based upon the fuel reprocessing principle that
provides ecology friendly management of fission products and recycling of nuclear materials.
<strong>The</strong> strategic areas in SNF management are:
• establishment of a reliable system for long-term monitored SNF storage;
• development of SNF reprocessing technologies ;
• balanced involvement of the recycled nuclear materials in the nuclear fuel cycle;
• final isolation (disposal) of RW resulted from SNF reprocessing.
<strong>The</strong> prime purpose of SNF management Concept is to develop the strategy for SNF management in Russian Federation up to
2020 and for the future up to 2030 and to select key structural and technical approaches and effective mechanisms assuring the Concept
implementation.
To implement the Concept is to establish a State Unified System for SNF management, comprising all required legal, regulatory,
structural and financial mechanisms, as well as human resources and facilities.
<strong>The</strong> top priority at all stages of SNF management is to provide nuclear, radiation and ecological safety, physical protection and
control of fissile materials and not to impose excessive burden on future generations.
E) PLAN FOR SITE RELEASE OF DECOMMISSIONING PROJECT OF KRR-1&2 - 16287
Sang Bum Hong, Korea Atomic Energy Research Institute (Korea)
Its important to release criteria and survey procedures for site release from regulatory control in the decommissioning projects.
<strong>The</strong> objective of the plan for site cleanup should be considering the optimization a radiological protection of the public and environment.
In this study, the plan for site release was established the release criteria and survey design of the site and building of
KRR-1&2. <strong>The</strong> decommissioning project of KRR-1&2 was launched in January 1997. <strong>The</strong> work scopes during the reactor decommissioning
project are the dismantling of all the facilities and the removal of all the radioactive materials from the reactor site. After
confirming the removal of the radioactive material, the site and buildings will be returned to the Korea Electric Power Company
(KEPCO).
Some of the countries already developed and applied the release criteria, but the criteria has not establish in Korea. <strong>The</strong> release
criteria for site and building were set up by considering the final purpose of site and comparing the dose criteria used in Germany
and USA. Based on these result, the site specific release levels was calculated for the KRR site and building by using RESRAD
and RESRAD-Build codes.
<strong>The</strong> survey design was carried out by using the MARSSIM, the site and building could be classified by class 2 or class 3 based
on the decontamination results and potential contamination. <strong>The</strong> site and building were divided and calculated the number of sample
in each survey unit. Based on the survey design, the dose rate, in situ gamma spectrometry was measured using survey meter
connected with GPS systems on the surface soil of the site.
F) PRESENT STATE OF REMEDIATION OF MECSEK URANIUM MINES, RADIOACTIVE PARAMETERS - 16337
András Várhegyi, MECSEK-ÖKO Environment Co. (Hungary);
Zorán Gorjánácz, MECSEKÉRC Environment Co. (Hungary); János Somlai, Pannon University (Hungary)
In the period of 19561997 Uranium ore mining and chemical ore processing activity had taken place in Mecsek Mountains,
SW Hungary. After closing the mines, a huge environment remediation project started at the affected area what is almost completed
by 2009; only sporadic soil contaminations are re-mained. <strong>The</strong> results of radiological monitoring satisfactorily indicated the
decrease of radiation levels, both on the work-places and in the close living sites. <strong>The</strong> original radiation back-ground was gradually
reconstructed while all the waste rock piles and tailings ponds were covered. During the field works, the population of the most
117