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Volumn 140, Issue 1, 2002, Pages 94-112

Relationship among performance of geologic repositories, canister-array configuration, and radionuclide mass in waste

Author keywords

Canister multiplicity; Radionuclide mass reduction effects; Repository performance measures

Indexed keywords

GEOLOGICAL REPOSITORIES; GROUNDWATER; RADIOACTIVE WASTE STORAGE; RADIOISOTOPES;

EID: 0036772818     PISSN: 00295450     EISSN: None     Source Type: Journal    
DOI: 10.13182/NT02-A3326     Document Type: Article
Times cited : (29)

References (18)
  • 2
    • 0005082997 scopus 로고
    • Massachusetts Institute of Technology Int. Conf. Next Generation of Nuclear Power Technology, UCB-NE-4176, University of California, Berkeley
    • T.H. Pigford, "Actinide Burning and Waste Disposal," Massachusetts Institute of Technology Int. Conf. Next Generation of Nuclear Power Technology, UCB-NE-4176, University of California, Berkeley (1990).
    • (1990) Actinide Burning and Waste Disposal
    • Pigford, T.H.1
  • 3
    • 0031647801 scopus 로고    scopus 로고
    • Integrated radionuclide transport model for a high-level waste repository in water-saturated geologic formations
    • J. Ahn, "Integrated Radionuclide Transport Model for a High-Level Waste Repository in Water-Saturated Geologic Formations," Nucl. Technol., 121, 24 (1998).
    • (1998) Nucl. Technol. , vol.121 , pp. 24
    • Ahn, J.1
  • 8
    • 0011233870 scopus 로고
    • SKB91: Final disposal of spent nuclear fuel. Importance of the bedrock for safety
    • Svensk Karnbranslehantering Ab
    • "SKB91: Final Disposal of Spent Nuclear Fuel. Importance of the Bedrock for Safety," SKB Technical Report 92-20, Svensk Karnbranslehantering Ab (1992).
    • (1992) SKB Technical Report , vol.92 , Issue.20
  • 9
    • 0005026944 scopus 로고    scopus 로고
    • Possibility of safety improvement for vitrified HLW geologic disposal by partitioning and transmutation
    • Jackson Hole, Wyoming, August 29-September 3, 1999, American Nuclear Society
    • J. Ahn, "Possibility of Safety Improvement for Vitrified HLW Geologic Disposal by Partitioning and Transmutation," Proc. Global '99, Int. Conf. Future Nuclear Systems, Jackson Hole, Wyoming, August 29-September 3, 1999, American Nuclear Society (1999).
    • (1999) Proc. Global '99, Int. Conf. Future Nuclear Systems
    • Ahn, J.1
  • 10
    • 0032635371 scopus 로고    scopus 로고
    • Criticality safety assessment for a conceptual high-level-waste repository in water-saturated geologic media
    • J. Ahm, "Criticality Safety Assessment for a Conceptual High-Level-Waste Repository in Water-Saturated Geologic Media," Nucl. Technol., 126, 303 (1999).
    • (1999) Nucl. Technol. , vol.126 , pp. 303
    • Ahn, J.1
  • 12
    • 0027239292 scopus 로고
    • 237Np decay chain limited by their elemental solubilities in the artificial barriers of high-level radioactive waste repositories
    • 237Np Decay Chain Limited by Their Elemental Solubilities in the Artificial Barriers of High-Level Radioactive Waste Repositories," Nucl. Technol., 101, 79 (1993).
    • (1993) Nucl. Technol. , vol.101 , pp. 79
    • Ahn, J.1    Suzuki, A.2
  • 14
    • 0005045595 scopus 로고    scopus 로고
    • Development of object-oriented simulation code for repository performance assessment
    • K. Tsujimoto and J. Ahn, "Development of Object-Oriented Simulation Code for Repository Performance Assessment," Trans. Am. Nucl. Soc., 81, 54 (1999).
    • (1999) Trans. Am. Nucl. Soc. , vol.81 , pp. 54
    • Tsujimoto, K.1    Ahn, J.2
  • 15
    • 3342958533 scopus 로고    scopus 로고
    • Standards for protection against radiation
    • Title 10, Part 20
    • "Standards for Protection Against Radiation," Title 10, Part 20, Code of Federal Regulation.
    • Code of Federal Regulation
  • 18
    • 0030623054 scopus 로고    scopus 로고
    • Long-term criticality control in radio-active waste disposal facilities
    • C. Forsberg, "Long-Term Criticality Control in Radio-active Waste Disposal Facilities," Nucl. Safety, 38, 1, 60 (1997).
    • (1997) Nucl. Safety , vol.38 , Issue.1 , pp. 60
    • Forsberg, C.1


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.