An Analysis of Carbon-14 Metabolism for Internal Dosimetry at CANDU Nuclear Power Plants

중수로 원전 종사자의 방사선량 평가를 위한 $^{14}C$ 인체대사모델 분석

  • Published : 2003.09.30

Abstract

Carbon-14 is one of the major radionuclides released by CANDU Nuclear Power Plants(NPPs). It is almost always emitted as gas through the stack. From CANDU NPPs about 95% of all carbon-14 is released as carbon dioxide. Carbon-14 is a low energy beta emitter which, therefore, gives only a small skin dose from external radiation. As carbon dioxide Is physiologically rather inert gases for man's metabolism, the inhalation dose is probably less than 1 % of the ingestion dose. But this source of carbon-14, formed in a closed, nor-oxidative environment, was subsequently released into the workplace as an insoluble particulate when these systems were opened lip for re-tubing at CANDU NPPs. As a part of the improvement of dosimetry program at Wolsong Nuclear Power Plants, the carbon-14 metabolism based on references was investigated and studied to setup the internal dosimetry program due to inhalation of carbon-14.

$^{14}C$은 중수로원전에서 연돌(Stack)을 통해 방출되는 중요한 방사성 핵종중의 하나로, 대략 95% 가량이 이산화탄소의 형태로 발생되고 방출되고 있다. 방사성탄소는 발생에너지가 낮은 베타 방출체로서 외부피폭은 크게 영향을 미치지 않는다. 따라서 중수로에서 탄소는 흡입이나 섭취를 통해 작업자 체내로 유입되는 경우에만 내부피폭을 일으키고 있다. 일반적으로 탄소는 신체에서 불활성 기체와 같은 거동을 보이기 때문에 섭취경로에 의한 피폭이 흡입경로에 의한 피폭보다 훨씬 높은 것으로 알려져 있다. 따라서 작업장에서 탄소의 흡입에 의한 방사선 피폭은 거의 일어나지 않으나 캐나다 원전의 압력관 교체 작업시 아주 소량의 피폭을 일으킨 경험이 있다. 본 논문은 원전 작업장에서 일어날 수 있는 방사성탄소의 흡입에 대비하여 방사선 피폭평가를 위한 방사선방호 프로그램을 수립할 목적으로 방사성탄소의 인체 대사모델 등에 대한 분석을 수행하였다.

Keywords

References

  1. 원자력발전소 주변 환경방사선 조사 보고서, 한국수력원자력(주), (2001)
  2. 원자력발전소 방사선관리 연보, 한국수력원자력(주), (2001)
  3. 캐나다 OPG 소속 방사선방호 전문가 초청결과 보고서, TM.00NE21.P2001.641(2002)
  4. M. J. Kabat and D. J. Gorman, Carbon-14 in Ontario Hyder's Nuclear Stations : Production, System and Effluent Levels, Dosimetry and Environmental Data, SSDIR-81-24, (1980)
  5. H. S. Winchell and H. Stahelin, et at, 'Kinetic of C02-HC03 in Normal Adult Males,' J. Nucl. Med. 11, 711, (1970)
  6. A. W. Phipps, G. M. Kendall, T. P. Fell, and J. D. Harrison, 'Doses from Radioactive Material,' Rad. Prot. Dosi. 30, 191, (1988)
  7. J. E. Peterson and R D. Stewart, 'Absorption and Elimination of Carbon Monoxide by Inactive Young Men,' Arch Environ. Health, 21, 165, (1970) https://doi.org/10.1080/00039896.1970.10667215
  8. C. R. Boss and P. J. Allsop, Radiactive effluents from CANDU-6 reactors, AECL report TR-533 (1994)
  9. M. J. Kabat and D. J. Gorman, Carbon-14 in Ontario Hydro's nuclear stations: production, system and effluent levels, dosimetry and enviromental data. Ontario Hydro, Safety Service Department, Information report SSD-IR-80-3 (1980)
  10. The management of carbon-14 in Canadian nuclear facilities, ACRP-14 (1995)
  11. International Commission on Radiation Protection, Evaluation of Radiation Doses to Body Tissues from Internal Contamination Due to Occupational Exposer, New York : Pergamon Press; ICRP Publication 10
  12. International Commission on Radiation Protection. Limits for intakes of radionuclides by workers. New York : Pergamon Press; ICRP Publication 30, 1979 - 1982
  13. DW. Whillans and M. J. Hayes, Dose Assessment Programme for Exposure to Carbon-14 Dioxide, Ontario Power Generation (1995)
  14. D. W. Whillans and J. R. Johnson, Interpretation of Urinary Excretion Rate Data in the Assessment of Uptake of Carbon-Id, IAEA-SM-276/50 (1985)
  15. AECB, Bioassay Reference Technical Criteria - Radiocarbon Bioassay - Report of the AECB Working Group on Internal Dosimetry (1994)