방사선산업학회지 (Journal of Radiation Industry)

한국방사선산업학회 (Korean Society of Radiation Industry)
권호 표지
DOI QR코드

DOI QR Code

결정론적 및 확률론적 방법을 이용한 방사성폐기물 운반 위험도 평가 비교·분석

Comparison of Radioactive Waste Transportation Risk Assessment Using Deterministic and Probabilistic Methods

  • 곽민우 (경희대학교 원자력공학과) ;
  • 김혁재 (경희대학교 원자력공학과) ;
  • 오가은 (경희대학교 원자력공학과) ;
  • 이신동 (경희대학교 원자력공학과) ;
  • 김광표 (경희대학교 원자력공학과)
  • Min Woo Kwak (Department of Nuclear Engineering, Kyung Hee University) ;
  • Hyeok Jae Kim (Department of Nuclear Engineering, Kyung Hee University) ;
  • Ga Eun Oh (Department of Nuclear Engineering, Kyung Hee University) ;
  • Shin Dong Lee (Department of Nuclear Engineering, Kyung Hee University) ;
  • Kwang Pyo Kim (Department of Nuclear Engineering, Kyung Hee University)
  • 투고 : 2023.03.07
  • 심사 : 2023.03.14
  • 발행 : 2023.03.31
PDF 다운로드
⟨ 이전 논문 다음 논문 ⟩

초록

When assessing the risk of radioactive wastes transportation on land, computer codes such as RADTRAN and RISKIND are used as deterministic methods. Transportation risk assessment using the deterministic method requires a relatively short assessment time. On the other hand, transportation risk assessment using the probabilistic method requires a relatively long assessment time, but produces more reliable results. Therefore, a study is needed to evaluate the exposure dose using a deterministic method that can be evaluated relatively quickly, and to compare and analyze the exposure dose result using a probabilistic method. The purpose of this study is to evaluate the exposure dose during transportation of radioactive wastes using deterministic and probabilistic methods, and to compare and analyze them. For this purpose, the main exposure factors were selected and various exposure situations were set. The distance between the radioactive waste and the receptor, the size of the package, and the speed of vehicle were selected as the main exposure factors. The exposure situation was largely divided into when the radioactive wastes were stationary and when they were passing. And the dose (rate) model of the deterministic overland transportation risk assessment computer code was analyzed. Finally, the deterministic method of the RADTRAN computer code and the RISKIND computer code and the probabilistic method of the MCNP 6 computer code were used to evaluate the exposure dose in various exposure situations during transportation of radioactive wastes. Then we compared and analyzed them. As a result of the evaluation, the tendency of the exposure dose (rate) was similar when the radioactive wastes were stationary and passing. For the same situation, the evaluation results of the RADTRAN computer code were generally more conservative than the results of the RISKIND computer code and the MCNP 6 computer code. The evaluation results of the RISKIND computer code and the MCNP 6 computer code were relatively similar. The results of this study are expected to be used as basic data for establishing the radioactive wastes transportation risk assessment system in Korea in the future.

키워드

과제정보

본 연구는 원자력안전위원회의 재원으로 한국원자력안전재단의 지원을 받아 수행한 원자력안전연구사업의 연구결과입니다(No. 2106041).

참고문헌

  1. MOTIE. 2020. Korean 2nd Basic Plan for the Management of LILW.
  2. Weiner RF, Neuhauser KS, Heames TJ, O'Donnell BM and Dennis ML. 2014. RADTRAN 6 Technical Manual. Sandia National Laboratories. SAND2014-0780.
  3. Yuan YC, Chen SY, Biwer BM and LePoire DJ. 1995. RISKIND - A Computer Program for Calculating Radiological Consequences and Health Risks from Transportation of Spenct Nuclear Fuel. Argonne National Laboratory. ANL/EAD-1.
  4. Steinman RL and Kearfott KJ. 2000. A Comparison of the RADTRAN 5 and RISKIND 1.11 Incident-Free Dose Models. WM'00 Conference.
  5. Steinman RL, Weiner RF and Kearfott KJ. 2002. A Comparison of Transient Dose Model Predictions and Experimental Measurements. Health Physics 83(4):504-511. https://doi.org/10.1097/00004032-200210000-00008
  6. Weiner RF and Neuhauser KS. 1991. Conser vatism of RADTRAN Line-Source Model for Estimating Worker Exposures. PATRAM'92.
  7. Biwer BM, Arnish JJ, Kamboj S and Chen SY. 1997. RISKIND Verification and Benchmark Comparisons. Argonne National Laboratory. ANL/EAD/TM-74.
  8. Brumburgh GP and Alesso HP. 1993. A Comparison of RISKIND and RADTRAN 4. Lawrence Livermore National Laboratory. UCRL-ID-115618.
  9. Maheras SJ and Pippen HK. 1995. Validation of the Transportation Computer Codes HIGHWAY, INTERLINE, RADTRAN 4, and RISKIND. Idaho National Engineering Laboratory. DOE/ID-10511.
  10. NRC. 1977. Final Environmental Statement on the Transportation of Radioactive Material by Air and Other Modes. NUREG-0170.
  11. Taylor JM and Daniel SL. 1977. RADTRAN: A Computer Code to Analyze Transportation of Radioactive Material. Sandia National Laboratories. SAND76-0243.
  12. Taylor JM and Daniel SL. 1977. RADTRAN II: Revised Computer Code to Analyze Transportation of Radioactive Material. Sandia National Laboratories. SAND80-1943.
  13. Madsen MM, Taylor JM and Ostmeyer RM. 1986. RADTRAN III. Sandia National Laboratories. SAND84-0036.
  14. Neuhauser KS and Kanipe FL. 1992. RADTRAN 4: User Guide. Sandia National Laboratories. SAND89-2370.
  15. Neuhauser KS, Kanipe FL and Weiner RF. 2000. RADTRAN 5 Technical Manual. Sandia National Laboratories. SAND2000-1256.
  16. Yuan YC, Chen SY, LePoire DJ and Rothman R. 1993. RISKIND - A Computer Program for Calculating Radiological Consequences and Health Risks from Transportation of Spenct Nuclear Fuel. Argonne National Laboratory. ANL/EAIS-6, Rev. 0.
  17. Chen SY and Yuan YC. 1988. Calculation of Radiation Dose Rates from a Spent Nuclear Fuel Shipping Cask. Transactions of the American Nuclear Society 56:110-112.
  18. LANL. 2017. MCNP User's Manual Code Version 6.2. Los Alamos National Laboratory Tech. Rep. LA-UR-17-29981.
  19. Sandquist GM, Rogers VC, Sutherland AA and Merrel GB. 1985. Exposures and Health Effects from Spent Nuclear Fuel Transportation. Rogers and Associates Engineering Corporation. RAE-8339/12-1.
  20. Weiner RF and Neuhauser KS. 1991. Near-Field Radiation Doses from Trnasported Spent Nuclear Fuel. Sandia National Laboratories. SAND91-2060C.
  21. RSIC. 1981. CASK-81: 22 Neutron, 18 Gamma-Ray Group, P3, Cross Sections for Shipping Cask Analysis. Radiation Shielding Information Center, Oak Ridge National Laboratory. DLC-23F.