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      KCI등재 SCOPUS

      Review of Instant Release Fractions of Long-lived Radionuclides in CANDU and PWR Spent Nuclear Fuels Under the Geological Disposal Conditions

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      https://www.riss.kr/link?id=A108182450

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      다국어 초록 (Multilingual Abstract)

      Several countries, including Korea, are considering the direct disposal of spent nuclear fuels. The radiological safety assessment results published after a geological repository closure indicate that the instant release is the main radiation source r...

      Several countries, including Korea, are considering the direct disposal of spent nuclear fuels. The radiological safety assessment results published after a geological repository closure indicate that the instant release is the main radiation source rather than the congruent release. Three Safety Case reports recently published were reviewed and the IRF values of seven long-lived radionuclides, including relevant experimental results, were compared. According to the literature review, the IRF values of both the CANDU and low burnup PWR spent fuel have been experimentally measured and used reasonably. In particular, the IRF values of volatile long-lived nuclides, such as 129I and 135Cs, were estimated from the FGR value. Because experimental leaching data regarding high burnup spent nuclear fuels are extremely scarce, a mathematical modelling approach proposed by Johnson and McGinnes was successfully applied to the domestic high burnup PWR spent nuclear fuel to derive the IRF values of iodine and cesium. The best estimate of the IRF was 5.5% at a discharge burnup of 55 GWd tHM−1.

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      참고문헌 (Reference)

      1 S. Stroes-Gascoyne, "The Relationship Between Gap Inventories of Stable Xenon, 137Cs, and 129I in Used CANDU Fuel" 77 (77): 320-330, 1987

      2 H. Kleykamp, "The Chemical State of the Fission Products in Oxide Fuels" 131 (131): 221-246, 1985

      3 F. Garisto, "Technetium-99: Review of Properties Relevant to a Canadian Geological Repository" Ontario Power Generation 2002

      4 P. Lovera, "Synthesis Report on the Relevant Diffusion Coefficients of Fission Products and Helium in Spent Nuclear Fuels" Commissariat à l’énergie atomique 2003

      5 L. Johnson, "Spent Fuel Radionuclide Source-term Model for Assessing Spent Fuel Performance in Geological Disposal. Part I: Assessment of the Instant Release Fraction" 346 (346): 56-65, 2005

      6 L.O. Werme, "Spent Fuel Performance Under Repository Conditions: A Model for Use in SR-Can" Svensk Kärnbränslehantering AB 2004

      7 M. Gobien, "Sixth Case Study: Reference Data and Codes" Nuclear Waste Management Organization 2016

      8 Posiva Oy, "Safety Case for the Disposal of Spent Nuclear Fuel at Olkiluoto-Models and Data for the Repository System 2012" Posiva Oy 2013

      9 C.N. Wilson, "Results From NNWSI Series 2 Bare Fuel Dissolution Tests" Pacific Northwest Laboratory 1990

      10 L.H. Johnson, "Release of Segregated Nuclides From Spent Fuel" Svensk Kärnbränslehantering AB 1997

      1 S. Stroes-Gascoyne, "The Relationship Between Gap Inventories of Stable Xenon, 137Cs, and 129I in Used CANDU Fuel" 77 (77): 320-330, 1987

      2 H. Kleykamp, "The Chemical State of the Fission Products in Oxide Fuels" 131 (131): 221-246, 1985

      3 F. Garisto, "Technetium-99: Review of Properties Relevant to a Canadian Geological Repository" Ontario Power Generation 2002

      4 P. Lovera, "Synthesis Report on the Relevant Diffusion Coefficients of Fission Products and Helium in Spent Nuclear Fuels" Commissariat à l’énergie atomique 2003

      5 L. Johnson, "Spent Fuel Radionuclide Source-term Model for Assessing Spent Fuel Performance in Geological Disposal. Part I: Assessment of the Instant Release Fraction" 346 (346): 56-65, 2005

      6 L.O. Werme, "Spent Fuel Performance Under Repository Conditions: A Model for Use in SR-Can" Svensk Kärnbränslehantering AB 2004

      7 M. Gobien, "Sixth Case Study: Reference Data and Codes" Nuclear Waste Management Organization 2016

      8 Posiva Oy, "Safety Case for the Disposal of Spent Nuclear Fuel at Olkiluoto-Models and Data for the Repository System 2012" Posiva Oy 2013

      9 C.N. Wilson, "Results From NNWSI Series 2 Bare Fuel Dissolution Tests" Pacific Northwest Laboratory 1990

      10 L.H. Johnson, "Release of Segregated Nuclides From Spent Fuel" Svensk Kärnbränslehantering AB 1997

      11 S. Stroes-Gascoyne, "Release of 14C From the Gap and Grain-Boundary Regions of Used CANDU Fuels to Aqueous Solutions" 14 (14): 385-392, 1994

      12 G. Vesterlund, "Recent ABB Fuel Design and Performance Experience" ANS 62-70, 1994

      13 L. Johnson, "Rapid Aqueous Release of Fission Products From High Burn-up LWR Fuel: Experimental Results and Correlations With Fission gas Release" 420 (420): 54-62, 2012

      14 이종열 ; 김인영 ; 주희재 ; 최희주 ; 조동건, "Proposal of an Improved Concept Design for the Deep Geological Disposal System of Spent Nuclear Fuel in Korea" 한국방사성폐기물학회 18 : 1-19, 2020

      15 J.L. Cormenzana, "Probabilistic Sensitivity Analysis for the ‘Initial Defect in the Canister’ Reference Model" 2013

      16 Nuclear Waste Management Organization, "Postclosure Safety Assessment of a Used Fuel Repository in Crystalline Rock" NWMO 2017

      17 Y.H. Koo, "Pore Pressure and Swelling in the Rim Region of LWR High Burnup UO2 Fuel" 295 (295): 213-220, 2001

      18 L.H. Johnson, "Partitioning of Radionuclides in Swiss Power Reactor Fuels" National Cooperative for the Disposal of Radioactive Waste 2002

      19 K. Lassmann, "Modelling the High Burnup UO2 Structure in LWR Fuel" 226 (226): 1-8, 1995

      20 S. Stroes-Gascoyne, "Measurements of Instant-Release Source Terms for 137Cs, 90Sr, 99Tc, 129I and 14C in Used CANDU Fuels" 238 (238): 264-277, 1996

      21 Svensk Kärnbränslehantering AB, "Long-term Safety for the Final Repository for Spent Nuclear Fuel at Forsmark" SKB 2011

      22 W. J. Gray, "Inventories of Iodine-129 and Cesium-137in the Gaps and Grain Boundaries of LWR Spent Fuels" 556 : 487-494, 1999

      23 D. Serrano-Purroy, "Instant Release Fraction and Matrix Release of High Burn-up UO2Spent Nuclear Fuel: Effect of High Burn-up Structure and Leaching Solution Composition" 427 (427): 249-258, 2012

      24 E. Nordström, "Fission Gas Release Data for Ringhals PWRs" Svensk Kärnbränslehantering AB 2009

      25 L. Johnson, "Estimates of the Instant Release Fraction for UO2 and MOX Fuel at t=0" National Cooperative for the Disposal of Radioactive Waste 2004

      26 J.C. Tait, "Determination of Cl Impurities and 36Cl Instant Release From Used CANDU Fuels" MRS 465 : 503-510, 1997

      27 Svensk Kärnbränslehantering AB, "Data Report for the Safety Assessment SR-Site" SKB 2010

      28 Y.H. Koo, "Conservative Width of High-Burnup Structure in Light Water Reactor UO2 Fuel as a Function of Pellet Average Burnup" 164 (164): 337-347, 2008

      29 Y.M. Lee, "A GoldSim Model for the Safety Assessment of an HLW Repository" 51 (51): 746-759, 2009

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      학술지 이력

      학술지 이력
      연월일 이력구분 이력상세 등재구분
      2024 평가예정 해외DB학술지평가 신청대상 (해외등재 학술지 평가)
      2021-07-28 학술지명변경 한글명 : 방사성폐기물학회지 -> Journal of Nuclear Fuel Cycle and Waste Technology KCI등재
      2021-01-01 평가 등재학술지 유지 (해외등재 학술지 평가) KCI등재
      2020-01-01 평가 등재학술지 유지 (재인증) KCI등재
      2017-01-01 평가 등재학술지 유지 (계속평가) KCI등재
      2014-08-07 학술지명변경 외국어명 : Journal of Nuclear Fuel Cycle and Waste Technology (Korean) -> Journal of Nuclear Fuel Cycle and Waste Technology KCI등재
      2013-11-26 학술지명변경 외국어명 : Journal of the Korean Radioactive Waste Society -> Journal of Nuclear Fuel Cycle and Waste Technology (Korean) KCI등재
      2013-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2010-01-01 평가 등재학술지 선정 (등재후보2차) KCI등재
      2009-01-01 평가 등재후보 1차 PASS (등재후보1차) KCI등재후보
      2008-01-01 평가 등재후보학술지 유지 (등재후보1차) KCI등재후보
      2006-01-01 평가 등재후보학술지 선정 (신규평가) KCI등재후보
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      학술지 인용정보

      학술지 인용정보
      기준연도 WOS-KCI 통합IF(2년) KCIF(2년) KCIF(3년)
      2016 0.17 0.17 0.17
      KCIF(4년) KCIF(5년) 중심성지수(3년) 즉시성지수
      0.15 0.16 0.409 0.08
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