ICEM11 Final Program 9.7.11pm_ICEM07 Final Program ... - Events
ICEM11 Final Program 9.7.11pm_ICEM07 Final Program ... - Events
ICEM11 Final Program 9.7.11pm_ICEM07 Final Program ... - Events
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Session 39 Abstracts<br />
“ organizational measures concerning time of staffs or publics stay in the vicinity on conditionally released materials for<br />
individual performed scenarios and nuclide vectors.<br />
The article further describes VISIPLAN 3D ALARA calculation planning software tool, having been used for calculation of<br />
staffs and publics external exposure for individual scenarios. Several other parallel papers proposed for ICEM 11 are presenting<br />
selected details of the project.<br />
A-3) UNCERTAINTY ANALYSIS OF ACTIVITY MEASUREMENT OF NEW MONITORING SYSTEM<br />
FOR FREE-RELEASE FOR NPP A-1 DECOMMISSIONING, SLOVAKIA (wP-59244)<br />
Alojz Slaninka, VUJE, a.s./ Slovak University of Technology in Bratislava; Ondrej Slávik, VUJE, a.s.;<br />
Vladimir Necas, Slovak University of Technology (Slovakia)<br />
Within 2nd stage of decommissioning project of NPP A-1 in Slovakia it is necessary to decontaminate, monitor and if possible<br />
to free release large amounts of contaminated materials, mainly contaminated soil and concrete debris (thousands of tons). Their<br />
contamination is caused by dominant 137Cs (33 years after shutdown) that emits 661.65 keV gamma ray that can be easily detected<br />
by scintillation or semiconductor detectors. In this connection a new free release monitoring post with a large volume 600 L container<br />
counting geometry was designed and developed. The monitoring system is based on a pair of electrically cooled semiconductor<br />
HPGe detectors that are placed into a modifiable vertical or horizontal pair of lead collimators. The detectors are equipped<br />
with a Canberra Packard gammaspectrometry chain including proper characterised HPGe detectors type GC 3020. The vertical<br />
arrangement of the collimator ensures monitoring of materials in 200 l rotating drums. The horizontal one ensures monitoring of<br />
the one side of a 600 l rectangular container. The monitoring system is integrated with an industrial scale for determination of massic<br />
activities of measured materials and in addition by a rotating table in the case of 200 l drums monitoring. Full-energy peak detection<br />
efficiency polynomial curves…<br />
A-4) LASER REMOVAL OF CONTAMINANTS ON THE METAL SURFACE (wP-59343)<br />
Hui Jun Won, Jei Kwon Moon, Sun Hee Jung, Chong Hun Jung,<br />
Kune Woo Lee, Korea Atomic Energy Research Institute;<br />
Byung -Sun Choi, Korea Atomic Energy Research Institute (Korea)<br />
A Q-switched Nd:YAG laser with a 532 nm and 450 mJ/pulse was employed to study the decontamination characteristics of<br />
Type 304 stainless steel specimens and aluminum specimens artificially contaminated with CsNO3 , Co(NH4 ) 2 (SO4 )2, Eu2O3 and<br />
CeO2 , respectively. The relative atomic molar ratio of the contaminants on metal surface before and after laser irradiation was determined<br />
by EPMA. The morphology of specimen surface was examined by SEM. The optimum number of laser shots and the laser<br />
fluence for the system were determined. More than 98 % of CsNO3 , Co(NH4 ) 2 (SO4 )2, Eu2O3 on Type 304 stainless steel specimens<br />
could be removed by the circular type laser beam within the 16 laser shots at 13.3 J/cm2 and 10 Hz. The removal of contaminants<br />
on aluminum surface, however, was found to be more difficult by laser. Comparative study on the removal characteristics<br />
between the circular type laser beam and the string type laser beam was also performed. The variation of laser removal performance<br />
on the contaminants was investigated by changing the irradiation angle.<br />
A-5) INFLUENCE OF THE CONDITIONAL RELEASE OF THE MATERIALS WITH VERY<br />
LOW LEVEL OF RADIOACTIVITY ON THE ENVIRONMENT (wP -59132)<br />
Slavka Prvakova, University of Economics in Bratislava; Adela Mrskova, DECOM, A. S.;<br />
Jozef Pritrsky, DECOM (Slovakia)<br />
Significant amount of solid materials (metals, non-metals, building structures) that could be contaminated or activated is produced<br />
during operation and especially decommissioning of nuclear power plants. Considerable fraction of these materials has level<br />
of radioactivity close to the radiological limits allowing its safe release into the environment thereby could be potentially recycled<br />
within the special constructions, as for example tunnels, roads or bridges. If the requirements of legislation on the radiological limits<br />
for handling such material and long term safety of the constructions are fulfilled, contaminated material can be released in the<br />
form of recycled concrete, remelted steel, etc.<br />
The paper presents implementation of the IAEA and EC recommendations into the form of detailed analytical approaches with<br />
the aim to develop integrated scenarios and to analyse long-term influence of the conditional release of the material with very low<br />
level of radioactivity on the environment. Further, an estimation of the key input parameters characteristic for the specific conditions<br />
of Slovak case in order to fulfil the radiological limits according to the Slovak legislation is included. Analysed integrated scenarios<br />
represent surface or underground civil construction with radionuclides released directly into the geosphere and transported<br />
by a groundwater flow into the biosphere. The migration of radionuclides is modelled in the near-surface conditions with the advection<br />
as a dominant transport mechanism. Computer code GoldSim is used to evaluate the long-term safety assessment of the conditionally<br />
released material on the environment.<br />
A-6) CONDITIONAL RELEASE OF STEEL FROM DECOMMISSIONING<br />
IN A FORM OF REINFORCED CONCRETE (wP -59058)<br />
Jozef Pritrsky, DECOM; Miroslav Brodnan, University of Zilina;<br />
Vladimir Necas, Slovak University of Technology (Slovakia)<br />
The paper deals with the conditional release of low-level radioactive steel from decommissioning in a form of reinforced concrete.<br />
The main goal was to determine limits for radionuclides concentration and calculate the annual dose for a member of a critical<br />
group of public, which should not exceed 0.01 mSv/year (according to IAEA Safety Guide RS-G-1.7). Corrosion is the principle<br />
mechanism of radionuclides release in this case, therefore effort was devoted to assess the time-dependent rate of steel reinforcement<br />
corrosion. It was assumed, that concrete is initially highly alkaline (with pH of 12 to 13) because of hydration products<br />
such as calcium hydroxide, which keeps the steel surface passive and protected from corrosion. However, carbonic acid resulting<br />
from carbon dioxide and water in the atmosphere can react with these products to produce calcium carbonate. This process is<br />
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