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Estimating the Effects of a Potential Terrorist Attack on Railway Transport in Poland Using a Radiological Exposure Device

100%

Łukasiewicz J.

2014

tom 6(1)

85-96

The possibility of theft of radioactive material and its use in a terrorist attack is a serious problem for countries thathave, or plan to have, nuclear power stations on their territory. The terrorist attacks which took place in Tokyo in 1995 usingchemical weapons in the form of sarin, as well as attacks using biological weapons in the form of anthrax sent by mail in the UnitedStates after 2001, indicate that if such material fell into the hands of terrorist groups they would certainly use it to carry outan attack. In this article the author attempts to assess the effects of a potential attack on the Polish public rail transport systemusing radioactive materials. The article presents ways in which nuclear material can be used in terrorism, details selected radioactivesources that can be used in a radiological attack, and describes the medical effects of ionising radiation on the human body.The paper presents the results of calculations, for example the length of exposure to radiation of a human body during an attack witha Radiological Exposure Device (RED) using Cobalt-60 depending on the distance from the source of ionising radiation, and the riskof threat of a terrorist attack using radioactive material. The author also presents the consequences of a terrorist attack on publicrail transport, and determines the likelihood of successful placement by an attacking terrorist of ionising radiation sources in the railvehicle, and the probability that such an attack would use an RED.

Radiological assessment of atmospheric release from Tehran Research Reactor during normal operation by using Pc-Cream code

75%

Sadeghi N. , Ahangari R.

International Letters of Natural Sciences

2016

tom 54

In this work, radiological assessment of atmospheric release from Tehran’s Research Reactor (TRR) stack and assessment of public exposures under normal operation has been studied. To perform tasks mentioned above, Pc-Cream computer code which simulates Gaussian Dispersion air transport plume model as well as laboratory analysis of the soil and leaves samples and TLD (Thermo Luminescent Dosimeter) monitoring around the TRR site was used. Results of the Pc- Cream code showed that the annual committed and external dose received by the individual in the vicinity of the reactor is below the regulatory limit. Also, the results of laboratory analysis of available radionuclides in the soil and leaves samples showed that the concentrations are close to the background (K40=635, Th232=28, Cs137=0.29 up to 28.82, Ra226=25 (Bq1/Kg) in soil and K40=457, Be7≈70 (Bq/Kg) in leaves) and confirm the code results. The monitored dose values of the TLD detectors were positioned around the reactor within 500 m radius shows that the background dose in vicinity of TRR (113 μSv up to 150 μSv) is consistent with the background dose in Tehran province (125 μSv).

Patron nagrody Komisji Analitycznej Spektrometrii Atomowej KChA PAN

63%

Hulanicki A.

Analityka : nauka i praktyka

2008

tom nr 1

70-73

Decontamination of contaminated scrap metal by melting arisen from the decommissioning of nuclear power plant shut down after an accident

63%

Slimak A. , Necas V.

tom nr 4

16--20

The paper briefly describes the decontamination of radioactive scrap metal by melting as prospective technology to reduce the amount of metallic radioactive waste. Decontamination by melting presents a particular advantage of homogenising a number of radionuclides in the ingots and concentrating other radionuclides in the slag and dust filter resulting from the melting process, thus decontaminating the primary material. Presented paper also deals with the evaluation of an exposure of the workers during melting of radioactive scrap metal as well as impact of melting on the environment. According to obtained results, the effective doses absorbed by workers during the melting meets legislatively given limit 20 mSv annually.

W artykule krótko opisano dekontaminację radioaktywnego złomu poprzez przetapianie, jako potencjalną technologię do zmniejszenia ilości metalowych odpadów radioaktywnych. Szczególną zaletą dekontaminacji poprzez przetapianie jest homogenizacja szeregu radionuklidów we wlewkach i zatężenie innych radionuklidów w żużlu i na filtrze pyłu powstających podczas procesu przetapiania, a tym samym dekontaminacji materiału podstawowego. Prezentowana praca dotyczy również oceny ekspozycji pracowników podczas przetapiania radioaktywnego złomu, jak również wpływu przetapiania na środowisko. Według uzyskanych wyników, skuteczne dawki pochłaniane przez pracowników podczas przetapiania spełniają ustawowy limit 20 mSv rocznie.

Międzynarodowa wystawa atomowa w Amsterdamie w roku 1957

51%

I.V.

Wszechświat

1957

nr 01

Izotopy radioaktywne w badaniach nad absorpcją liściową

51%

I.V.

Wszechświat

1957

nr 05