Comparative Study of the γH2AX Foci Forming in Human Lung Fibroblasts Incubated in Media Containing Tritium-Labeled Thymidine or Amino Acids.

We compared the formation of γH2AX foci (marker of DNA double-strand breaks) in human lung fibroblasts (MRC-5 line) during their 24-h incubation in a medium containing 3H-labeled thymidine or amino acids (glycine, alanine, and proline) with specific radioactivity from 100 to 400 MBq/liter. A linear dependence of changes in the number of γH2AX foci on the specific radioactivity of the medium was revealed. The quantitative yield of DNA double-strand breaks under the influence of 3H-thymidine was more than 2-fold higher than under the influence of 3H-labeled amino acids. Comparative analysis of the yields of DNA double-strand breaks during cell incubation with 3H-labeled amino acids showed that 3H-alanine produced more pronounced effect that 3H-proline, which is consistent with the data on the content of their non-radioactive analogs in chromatin proteins.

Comparative Analysis of the Formation of γH2AX Foci in Human Mesenchymal Stem Cells Exposed to 3H-Thymidine, Tritium Oxide, and X-Rays Irradiation.

We performed a comparative study of the formation of γН2АХ foci (a marker of DNA doublestrand breaks) in human bone marrow mesenchymal stem cells after 24-h incubation with 3Н-thimidin and tritium oxide with low specific activities (50-800 MBq/liter). The dependence of the number of γH2AX foci on specific activity of 3H-thymidine was described by a linear equation y=2.21+43.45x (R2=0.96), where y is the number of γH2AX foci per nucleus and x is specific activity in 1000 MBq/liter. For tritium oxide, the relationship was described by a linear equation y=2.52+6.70x (R2=0.97). Thus, the yield of DNA double-strand breaks after exposure to 3H-thymidine was 6.5-fold higher than after exposure to tritium oxide. Comparison of the effects of tritium oxide and X-ray radiation on the yield of DNA double-strand breaks showed that the relative biological efficiency of tritium oxide in a dose range of 3.78-60.26 mGy was 1.6-fold higher than that of X-ray radiation. Improvement of the methods of analysis of DNA double-strand breaks repair foci is highly promising in the context of creation of highly sensitive biodosimetry technologies for tritium compounds in humans.

[Problems of safety regulation under radioactive waste management in Russia].

Analysis of the requirements of Federal Law N 190 "About radioactive waste management and incorporation of changes into some legislative acts of the Russian Federation", as well as normative-legislative documents actual and planned to be published related to provision of radiation protection of the workers and the public have been done. Problems of safety regulation raised due to different approaches of Rospotrebnadzor, FMBA of Russia, Rostekhnadzor and Minprirody with respect to classification and categorization of the radioactive wastes, disposal, exemption from regulatory control, etc. have been discussed in the paper. Proposals regarding improvement of the system of safety regulation under radioactive waste management and of cooperation of various regulatory bodies have been formulated.

Radiological protection regulation during spent nuclear fuel and radioactive waste management in the western branch of the Federal State Unitary Enterprise 'SevRAO'.

The site of temporary storage of spent nuclear fuel and radioactive waste, situated at Andreeva Bay in Northwest Russia, was developed in the 1960s, and it has carried out receipt and storage of fresh and spent nuclear fuel, and solid and liquid radioactive waste generated during the operation of nuclear submarines and nuclear-powered icebreakers. The site is now operated as the western branch of the Federal State Unitary Enterprise, SevRAO. In the course of operation over several decades, the containment barriers in the Spent Nuclear Fuel and Radioactive Waste storage facilities partially lost their containment effectiveness, so workshop facilities and parts of the site became contaminated with radioactive substances. This paper describes work being undertaken to provide an updated regulatory basis for the protection of workers during especially hazardous remediation activities, necessary because of the unusual radiation conditions at the site. It describes the results of recent survey work carried out by the Burnasyan Federal Medical Biophysical Centre, within a programme of regulatory cooperation between the Norwegian Radiation Protection Authority and the Federal Medical-Biological Agency of Russia. The survey work and subsequent analyses have contributed to the development of special regulations setting out radiological protection requirements for operations planned at the site. Within these requirements, and taking account of a variety of other factors, a continuing need arises for the implementation of optimisation of remediation at Andreeva Bay.

Regulatory supervision of sites for spent fuel and radioactive waste storage in the Russian northwest.

In the 1960s two technical bases for the Northern Fleet were created in the Russian northwest at Andreeva Bay in the Kola Peninsula and Gremikha village on the coast of the Barents Sea. They maintained nuclear submarines, receiving and storing radioactive waste and spent nuclear fuel. No further waste was received after 1985, and the technical bases have since been re-categorised as temporary storage sites. The handling of these materials to put them into a safe condition is especially hazardous because of their degraded state. This paper describes regulatory activities which have been carried out to support the supervision of radiological protection during recovery of waste and spent fuel, and to support regulatory decisions on overall site remediation. The work described includes: an assessment of the radiation situation on-site; the development of necessary additional regulatory rules and standards for radiation protection assurance for workers and the public during remediation; and the completion of an initial threat assessment to identify regulatory priorities. Detailed consideration of measures for the control of radiation exposure of workers and radiation exposure of the public during and after operations and emergency preparedness and response are complete and provided in sister papers. The continuing requirements for regulatory activities relevant to the development and implementation of on-going and future remediation activities are also outlined. The Norwegian Radiation Protection Authority supports the work, as part of the Norwegian Government's plan of action to promote improvements in radiation protection and nuclear safety in northwest Russia.

[Establishing of doses from the internal irradiation for the personnel of the Chernobyl AES and persons detailed in 1986-1987]. / Formirovanie doz ot vnutrennego oblucheniia dlia personala Chernobyl'skoi AES i komandirovannykh v 1986-1987 gg.

The paper is concerned with the results of measurements of characteristics of the air media in the zone of the damaged reactor as with the assessment of doses from internal irradiation on the basis of calculations of air media parameters and the results of actual measurements of the uptake and content of radionuclides in the personnel of the Chernobyl Nuclear Power Station and persons sent on mission there in 1986-1987, the results being obtained by indirect and direct biophysical methods of control of internal irradiation. The calculated data are well in accord with the results of actual measurements of the contents of radionuclides in the body. Internal irradiation of all tissues and organs, determined by the inhalation of a mixture of radionuclides, worked almost completely within the first year following the accident, the thyroid being the critical organ. In the next years internal irradiation for the personnel of the Chernobyl Nuclear Power Station was determined entirely by transuranic elements and was about 0.1 M.P.D annually for bone tissue. The value of a mean effective equivalent dose from internal irradiation in 50 years is 85 mSv for professionals, and a contribution of internal irradiation to the whole-body one over the first well as is 13%.