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Volumn 162, Issue 3, 2008, Pages 276-292

Stress analysis of coated particle fuel in graphite of high-temperature reactors

Author keywords

Coated particle fuel; High temperature reactors; Stress analysis

Indexed keywords

FUELS; GRAPHITE; HIGH TEMPERATURE ENGINEERING; NUCLEAR REACTORS; PEBBLE BED REACTORS; STRESS ANALYSIS;

EID: 46649093155     PISSN: 00295450     EISSN: None     Source Type: Journal    
DOI: 10.13182/NT08-A3956     Document Type: Article
Times cited : (22)

References (34)
  • 2
    • 0004444847 scopus 로고
    • Mathematical Model for Predicting Coated-Particle Behavior
    • Oct
    • J. W. PRADOS and J. L. SCOTT, "Mathematical Model for Predicting Coated-Particle Behavior," Nucl. Appl., 2, 402 (Oct. 1966).
    • (1966) Nucl. Appl , vol.2 , pp. 402
    • PRADOS, J.W.1    SCOTT, J.L.2
  • 3
    • 0027694943 scopus 로고
    • Analytical Solutions for Stresses in TRISO-Coated Particles
    • G. K. MILLER and R. G. BENNETT, "Analytical Solutions for Stresses in TRISO-Coated Particles," J. Nucl. Mater., 206, 35 (1993).
    • (1993) J. Nucl. Mater , vol.206 , pp. 35
    • MILLER, G.K.1    BENNETT, R.G.2
  • 4
    • 0003777721 scopus 로고    scopus 로고
    • Current Status and Future Development of Modular High Temperature Gas Cooled Reactor Technology
    • TECDOC 1198, International Atomic Energy Agency Feb
    • "Current Status and Future Development of Modular High Temperature Gas Cooled Reactor Technology," TECDOC 1198, International Atomic Energy Agency (Feb. 2001).
    • (2001)
  • 5
    • 8344290439 scopus 로고    scopus 로고
    • TIMCOAT: An Integrated Fuel Performance Model for Coated Particle Fuel
    • J. WANG, R. G. BALLINGER, and H. J. MACLEAN, "TIMCOAT: An Integrated Fuel Performance Model for Coated Particle Fuel," Nucl. Technol., 148, 68 (2004).
    • (2004) Nucl. Technol , vol.148 , pp. 68
    • WANG, J.1    BALLINGER, R.G.2    MACLEAN, H.J.3
  • 7
    • 33846784042 scopus 로고    scopus 로고
    • A Review of TRISO-Coated Particle Nuclear Fuel Performance Models
    • Oct
    • B. LIU, T. LIANG, and C. TANG, "A Review of TRISO-Coated Particle Nuclear Fuel Performance Models," Rare Metals, 25, 6, 337 (Oct. 2006).
    • (2006) Rare Metals , vol.25 , Issue.6 , pp. 337
    • LIU, B.1    LIANG, T.2    TANG, C.3
  • 8
    • 33745496620 scopus 로고    scopus 로고
    • Irradiation Performance and Modeling of the HTR-10 Coated Fuel Particles
    • T. X. LIANG, H. S. ZHAO, C. H. TANG, and K. VERFONDERN, "Irradiation Performance and Modeling of the HTR-10 Coated Fuel Particles," Nucl. Eng. Des., 236, 1922 (2006).
    • (2006) Nucl. Eng. Des , vol.236 , pp. 1922
    • LIANG, T.X.1    ZHAO, H.S.2    TANG, C.H.3    VERFONDERN, K.4
  • 10
    • 46649102787 scopus 로고    scopus 로고
    • A Technology Roadmap for Generation IV Nuclear Energy Systems, U.S. DOE Nuclear Energy Research Advisory Committee and the Generation IV International Forum (2002).
    • "A Technology Roadmap for Generation IV Nuclear Energy Systems," U.S. DOE Nuclear Energy Research Advisory Committee and the Generation IV International Forum (2002).
  • 11
    • 33644901747 scopus 로고    scopus 로고
    • Investigation of the Bounds on the Particle Packing in Pebble-Bed High Temperature Reactors
    • A. M. OUGOUAG, J. L. KLOOSTERMAN, W. F. G. VAN ROOIJEN, H. D. GOUGAR, and W. K. TERRY, "Investigation of the Bounds on the Particle Packing in Pebble-Bed High Temperature Reactors," Nucl. Eng. Des., 236, 669 (2006).
    • (2006) Nucl. Eng. Des , vol.236 , pp. 669
    • OUGOUAG, A.M.1    KLOOSTERMAN, J.L.2    VAN ROOIJEN, W.F.G.3    GOUGAR, H.D.4    TERRY, W.K.5
  • 12
    • 0030231621 scopus 로고    scopus 로고
    • Development of a Coated Fuel Particle Failure Model Under High Burnup Irradiation
    • K. SAWA, S. SHIOZAWA, K. MINATO, and K. FUKUDA, "Development of a Coated Fuel Particle Failure Model Under High Burnup Irradiation," J. Nucl. Sci. Technol., 33, 9, 712 (1996).
    • (1996) J. Nucl. Sci. Technol , vol.33 , Issue.9 , pp. 712
    • SAWA, K.1    SHIOZAWA, S.2    MINATO, K.3    FUKUDA, K.4
  • 13
    • 0029346726 scopus 로고
    • Stresses in a Spherical Pressure Vessel Undergoing Creep and Dimensional Changes
    • G. K. MILLER, "Stresses in a Spherical Pressure Vessel Undergoing Creep and Dimensional Changes," Int. J. Solids and Structures, 32, 14, 2077 (1995).
    • (1995) Int. J. Solids and Structures , vol.32 , Issue.14 , pp. 2077
    • MILLER, G.K.1
  • 14
    • 0029388289 scopus 로고
    • Considerations of Irradiation-Induced Transient Creep in Fuel Particle Modeling
    • Oct
    • G. K. MILLER, "Considerations of Irradiation-Induced Transient Creep in Fuel Particle Modeling," J. Nucl. Sci. Technol., 32, 10, 989 (Oct. 1995).
    • (1995) J. Nucl. Sci. Technol , vol.32 , Issue.10 , pp. 989
    • MILLER, G.K.1
  • 16
    • 36448948181 scopus 로고    scopus 로고
    • Updated Solutions for Stresses and Displacements in TRISO-Coated Fuel Particles
    • Idaho National Laboratory
    • G. K. MILLER, "Updated Solutions for Stresses and Displacements in TRISO-Coated Fuel Particles," Engineering Design File (EDF)-7042, Idaho National Laboratory (2006).
    • (2006) Engineering Design File (EDF)-7042
    • MILLER, G.K.1
  • 18
    • 0010317504 scopus 로고
    • Performance Evaluation of Modern HTR TRISO Fuels
    • Forschungszentrum Jülich July
    • R. GONTARD and H. NABIELEK, "Performance Evaluation of Modern HTR TRISO Fuels," HTA-IB-05/90, Forschungszentrum Jülich (July 1990).
    • (1990) HTA-IB-05/90
    • GONTARD, R.1    NABIELEK, H.2
  • 19
    • 36448943131 scopus 로고
    • Irradiation Damage in Graphite
    • p, IAEA-TECDOC-901 XA9642900, International Atomic Energy Agency
    • B. J. MARSDEN, "Irradiation Damage in Graphite," p. 17, IAEA-TECDOC-901 XA9642900, International Atomic Energy Agency (1995).
    • (1995) , pp. 17
    • MARSDEN, B.J.1
  • 20
    • 0025448333 scopus 로고
    • Irradiation Properties and Strength of a Fine-Grained Isotropic Graphite
    • T. OKU, M. ETO, and S. ISHIYAMA, "Irradiation Properties and Strength of a Fine-Grained Isotropic Graphite," J. Nucl. Mater., 172, 77 (1990).
    • (1990) J. Nucl. Mater , vol.172 , pp. 77
    • OKU, T.1    ETO, M.2    ISHIYAMA, S.3
  • 21
    • 0346338388 scopus 로고    scopus 로고
    • Lifetime Evaluation of Graphite Components for HTGRs
    • T. OKU and M. ISHIHARA, "Lifetime Evaluation of Graphite Components for HTGRs," Nucl. Eng. Des., 227, 209 (2004).
    • (2004) Nucl. Eng. Des , vol.227 , pp. 209
    • OKU, T.1    ISHIHARA, M.2
  • 23
    • 33847242939 scopus 로고    scopus 로고
    • Summary of Comparison and Analysis of Results from Exercises 1 & 2 of the OECD PBMR Coupled Neutronics /Thermal Hydraulics Transient Benchmark
    • Vancouver, British Columbia, Canada, September 10-14, American Nuclear Society , CD-ROM
    • P. MKHABELA, J. HAN, B. TYOBEKA, K. IVANOV, F. REITSMA, and E. SARTORI, "Summary of Comparison and Analysis of Results from Exercises 1 & 2 of the OECD PBMR Coupled Neutronics /Thermal Hydraulics Transient Benchmark," Proc. PHYSOR-2006, Vancouver, British Columbia, Canada, September 10-14, 2006, American Nuclear Society (2006) (CD-ROM).
    • (2006) Proc. PHYSOR-2006
    • MKHABELA, P.1    HAN, J.2    TYOBEKA, B.3    IVANOV, K.4    REITSMA, F.5    SARTORI, E.6
  • 25
    • 33847203645 scopus 로고    scopus 로고
    • Optimization of HTR Fuel to Reduce Fuel Particle Failure
    • Vancouver, British Columbia, Canada, September 10-14, American Nuclear Society , CD-ROM
    • B. BOER, J. L. KLOOSTERMAN, and A. M. OUGOUAG, "Optimization of HTR Fuel to Reduce Fuel Particle Failure," Proc. PHYSOR-2006, Vancouver, British Columbia, Canada, September 10-14, 2006, American Nuclear Society (2006) (CD-ROM).
    • (2006) Proc. PHYSOR-2006
    • BOER, B.1    KLOOSTERMAN, J.L.2    OUGOUAG, A.M.3
  • 26
    • 0003894050 scopus 로고    scopus 로고
    • SCALE-5. Modular Code System for Performing Standardized Computer Analysis for Licensing Evaluations
    • Oak Ridge National Laboratory 2005
    • "SCALE-5. Modular Code System for Performing Standardized Computer Analysis for Licensing Evaluations," Oak Ridge National Laboratory (2005).
  • 27
    • 0033204056 scopus 로고    scopus 로고
    • Analytical Calculation of the Average Dancoff Factor for a Fuel Kernel in a Pebble Bed High-Temperature Reactor
    • E. E. BENDE, A. H. HOGENBIRK, J. L. KLOOSTERMAN, and H. VAN DAM, "Analytical Calculation of the Average Dancoff Factor for a Fuel Kernel in a Pebble Bed High-Temperature Reactor," Nucl. Sci. Eng., 133, 2, 147 (1999).
    • (1999) Nucl. Sci. Eng , vol.133 , Issue.2 , pp. 147
    • BENDE, E.E.1    HOGENBIRK, A.H.2    KLOOSTERMAN, J.L.3    VAN DAM, H.4
  • 28
  • 33
    • 46649104397 scopus 로고    scopus 로고
    • PBMR Coupled Neutronics/Thermal Hydraulics Transient Benchmark - The PBMR-400 Core Design - Benchmark Description,
    • OECD, Technical Report Draft-V03, Nuclear Energy Agency Sep
    • OECD, "PBMR Coupled Neutronics/Thermal Hydraulics Transient Benchmark - The PBMR-400 Core Design - Benchmark Description," Technical Report Draft-V03, Nuclear Energy Agency (Sep. 2005).
    • (2005)
  • 34
    • 0035366610 scopus 로고    scopus 로고
    • Consideration of the Effects on Fuel Particle Behavior from Shrinkage Cracks in the Inner Pyrocarbon Layer
    • Mar
    • G. K. MILLER, D. A. PETTI, D. J. VARACALLE, and J. T. MAKI, "Consideration of the Effects on Fuel Particle Behavior from Shrinkage Cracks in the Inner Pyrocarbon Layer," J. Nucl. Mater., 295, 205 (Mar. 2001).
    • (2001) J. Nucl. Mater , vol.295 , pp. 205
    • MILLER, G.K.1    PETTI, D.A.2    VARACALLE, D.J.3    MAKI, J.T.4


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.