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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 />

102

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