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Volumn 153, Issue 2, 2006, Pages 172-183

A deep burn fuel management strategy for the incineration of military plutonium in the gas turbine-modular helium reactor modeled in a detailed three-dimensional geometry by the Monte Carlo continuous energy burnup code

Author keywords

[No Author keywords available]

Indexed keywords

CLADDING (COATING); CODES (STANDARDS); COST EFFECTIVENESS; GAS TURBINES; HELIUM; MONTE CARLO METHODS; NUCLEAR ENERGY; NUCLEAR REACTORS; PLUTONIUM; THREE DIMENSIONAL;

EID: 33745530266     PISSN: 00295639     EISSN: None     Source Type: Journal    
DOI: 10.13182/NSE06-A2603     Document Type: Article
Times cited : (7)

References (49)
  • 1
    • 0141818957 scopus 로고    scopus 로고
    • The burnup capabilities of the deep burn modular helium reactor analyzed by the Monte Carlo continuous energy code MCB
    • A. TALAMO, W. GUDOWSKI, and F. VENNERI, "The Burnup Capabilities of the Deep Burn Modular Helium Reactor Analyzed by the Monte Carlo Continuous Energy Code MCB," Ann. Nucl. Energy, 31, 2, 173 (2004).
    • (2004) Ann. Nucl. Energy , vol.31 , Issue.2 , pp. 173
    • Talamo, A.1    Gudowski, W.2    Venneri, F.3
  • 2
    • 4444238018 scopus 로고    scopus 로고
    • Key physical parameters and temperature reactivity coefficients of the deep burn modular helium reactor fueled with LWRs waste
    • A. TALAMO, W. GUDOWSKI, J. CETNAR, and F. VENNERI, "Key Physical Parameters and Temperature Reactivity Coefficients of the Deep Burn Modular Helium Reactor Fueled with LWRs Waste,"Ann. Nucl. Energy, 31, 16, 1913 (2004).
    • (2004) Ann. Nucl. Energy , vol.31 , Issue.16 , pp. 1913
    • Talamo, A.1    Gudowski, W.2    Cetnar, J.3    Venneri, F.4
  • 3
    • 13244277620 scopus 로고    scopus 로고
    • Comparative studies of ENDF/B-6.8, JEF-2.2 and JENDL-3.2 data libraries by Monte Carlo modeling of high temperature reactors on plutonium based fuel cycles
    • A. TALAMO and W. GUDOWSKI, "Comparative Studies of ENDF/B-6.8, JEF-2.2 and JENDL-3.2 Data Libraries by Monte Carlo Modeling of High Temperature Reactors on Plutonium Based Fuel Cycles," J. Nucl. Sci. Technol., 41, 12, 1228 (2004).
    • (2004) J. Nucl. Sci. Technol. , vol.41 , Issue.12 , pp. 1228
    • Talamo, A.1    Gudowski, W.2
  • 4
    • 22344434427 scopus 로고    scopus 로고
    • GT-MHR conceptual design description report
    • GA/NRC-337-02
    • "GT-MHR Conceptual Design Description Report," GA/NRC-337-02, General Atomics (2002).
    • (2002) General Atomics
  • 6
    • 0037738848 scopus 로고    scopus 로고
    • Neutronic features of the GT-MHR
    • N. KODOCHIGOV et al., "Neutronic Features of the GT-MHR," Nucl. Eng. Des., 222, 161 (2003).
    • (2003) Nucl. Eng. Des. , vol.222 , pp. 161
    • Kodochigov, N.1
  • 7
    • 0038685913 scopus 로고    scopus 로고
    • Modelling of HTRs with Monte Carlo: From a homogeneous to an exact heterogeneous core with microparticles, Ann
    • R. PLUKIENE and D. RIDIKAS, "Modelling of HTRs with Monte Carlo: From a Homogeneous to an Exact Heterogeneous Core with Microparticles," Ann. Nucl. Energy, 30, 1573 (2003).
    • (2003) Nucl. Energy , vol.30 , pp. 1573
    • Plukiene, R.1    Ridikas, D.2
  • 8
    • 0141573603 scopus 로고    scopus 로고
    • Reactor-based transmutation - Physics studies of the gas-cooled graphite-moderated deep burn reactor, GA-501-0-TRT-000140
    • A. BAXTER and M. FIKANI, "Reactor-Based Transmutation - Physics Studies of the Gas-Cooled Graphite-Moderated Deep Burn Reactor," GA-501-0-TRT-000140, General Atomics (2002).
    • (2002) General Atomics
    • Baxter, A.1    Fikani, M.2
  • 9
    • 0034795735 scopus 로고    scopus 로고
    • The application of gas-cooled reactor technologies to the transmutation of nuclear waste
    • A. BAXTER and C. RODRIGUEZ, "The Application of Gas-Cooled Reactor Technologies to the Transmutation of Nuclear Waste," Prog. Nucl. Energy, 38, 81 (2001).
    • (2001) Prog. Nucl. Energy , vol.38 , pp. 81
    • Baxter, A.1    Rodriguez, C.2
  • 10
    • 0034503578 scopus 로고    scopus 로고
    • Modular high temperature reactor contributing the global environmental protection
    • K. OHASHI, F. OKAMOTO, and H. HAYAKAWA, "Modular High Temperature Reactor Contributing the Global Environmental Protection," Prog. Nucl. Energy, 37, 307 (2000).
    • (2000) Prog. Nucl. Energy , vol.37 , pp. 307
    • Ohashi, K.1    Okamoto, F.2    Hayakawa, H.3
  • 11
    • 0034503892 scopus 로고    scopus 로고
    • Desirability of small reactors, HTGR in particular
    • Y. TSUCHIE, "Desirability of Small Reactors, HTGR in Particular," Prog. Nucl. Energy, 37, 253 (2000).
    • (2000) Prog. Nucl. Energy , vol.37 , pp. 253
    • Tsuchie, Y.1
  • 12
    • 0000027602 scopus 로고    scopus 로고
    • Project of the GT-MHR high temperature helium reactor with gas turbine
    • A. I. KIRYUSHIN et al., "Project of the GT-MHR High Temperature Helium Reactor with Gas Turbine," Nucl. Eng. Des., 173, 119 (1997).
    • (1997) Nucl. Eng. Des. , vol.173 , pp. 119
    • Kiryushin, A.I.1
  • 13
    • 4444367371 scopus 로고    scopus 로고
    • Where does the GT-MHR go from here?
    • J. D. WISTROM and W. A. SIMON, "Where Does the GT-MHR Go from Here?" Nucl. Eng. Int., 41, 10 (1996).
    • (1996) Nucl. Eng. Int. , vol.41 , pp. 10
    • Wistrom, J.D.1    Simon, W.A.2
  • 14
    • 27144527418 scopus 로고
    • Comparative economics of the GT-MHR and power generation alternatives
    • GA-A 21722
    • M. P. LABAR and W. A. SIMON, "Comparative Economics of the GT-MHR and Power Generation Alternatives," GA-A 21722, General Atomics (1994).
    • (1994) General Atomics
    • Labar, M.P.1    Simon, W.A.2
  • 16
    • 33745574131 scopus 로고    scopus 로고
    • Calculation of the decay heat removal transient by passive means for a direct cycle modular HTR
    • Petten, The Netherlands, April 22-24, 2002, International Atomic Energy Agency
    • A. WOAYE-HUNE and S. EHSTER, "Calculation of the Decay Heat Removal Transient by Passive Means for a Direct Cycle Modular HTR," Proc. 1st Int. Topl. Mtg. High Temperature Reactor Technology, Petten, The Netherlands, April 22-24, 2002, International Atomic Energy Agency (2002).
    • (2002) Proc. 1st Int. Topl. Mtg. High Temperature Reactor Technology
    • Woaye-Hune, A.1    Ehster, S.2
  • 17
    • 0035251490 scopus 로고    scopus 로고
    • Development of a simulation model and safety evaluation for a depressurization accident without reactor scram in an advanced HTGR
    • S. NAKAGAWA, A. SAIKUSA, and K. KUNTTOMI, "Development of a Simulation Model and Safety Evaluation for a Depressurization Accident Without Reactor Scram in an Advanced HTGR," Nucl. Technol., 133, 141 (2001).
    • (2001) Nucl. Technol. , vol.133 , pp. 141
    • Nakagawa, S.1    Saikusa, A.2    Kunttomi, K.3
  • 18
    • 4244088769 scopus 로고    scopus 로고
    • Courses and limitations of damage with air ingress accidents in HTR modules
    • Paris, France, September 27-29, 1999, Organization for Economic Cooperation and Development
    • W. FRÖHLING, "Courses and Limitations of Damage with Air Ingress Accidents in HTR Modules," Proc. 1st Information Exchange Mtg. Survey on Basic Studies in the Field of High Temperature Engineering, Paris, France, September 27-29, 1999, p. 173, Organization for Economic Cooperation and Development (1999).
    • (1999) Proc. 1st Information Exchange Mtg. Survey on Basic Studies in the Field of High Temperature Engineering , pp. 173
    • Fröhling, W.1
  • 20
    • 4444310708 scopus 로고    scopus 로고
    • Safety evaluation during a depressurization accident of the SFHTR
    • Beijing, China, November 2-4, 1998, IAEA-TECDOC-1210, International Atomic Energy Agency
    • S. NAKAGAWA, A. SAIKUSA, and K. KUNITOMI, "Safety Evaluation During a Depressurization Accident of the SFHTR," Proc. Int. Working Group on Gas-Cooled Reactors Mtg., Beijing, China, November 2-4, 1998, IAEA-TECDOC-1210, p. 77, International Atomic Energy Agency (1998).
    • (1998) Proc. Int. Working Group on Gas-cooled Reactors Mtg. , pp. 77
    • Nakagawa, S.1    Saikusa, A.2    Kunitomi, K.3
  • 21
    • 0030565967 scopus 로고    scopus 로고
    • Passive heat removal by vessel cooling system of HTTR during no forced cooling accidents
    • K. KUNITOMI, S. NAKAGAWA, and M. SHINOZACHI, "Passive Heat Removal by Vessel Cooling System of HTTR During No Forced Cooling Accidents," Nucl. Eng. Des., 166, 179 (1996).
    • (1996) Nucl. Eng. Des. , vol.166 , pp. 179
    • Kunitomi, K.1    Nakagawa, S.2    Shinozachi, M.3
  • 25
    • 0038172589 scopus 로고    scopus 로고
    • Investigation of irradiation behavior of siC-coated fuel particle at extended burnup
    • K. SAWA and T. TOBITA, "Investigation of Irradiation Behavior of SiC-Coated Fuel Particle at Extended Burnup," Nucl. Technol., 142, 250 (2003).
    • (2003) Nucl. Technol. , vol.142 , pp. 250
    • Sawa, K.1    Tobita, T.2
  • 26
    • 33745572466 scopus 로고    scopus 로고
    • Development of an integrated performance model for TRISO-coated gas reactor particle fuel
    • Petten, The Netherlands, April 22-24, 2002, International Atomic Energy Agency
    • G. K. MILLER, D. A. PETTI, and J. T. MAKI, "Development of an Integrated Performance Model for TRISO-Coated Gas Reactor Particle Fuel," Proc. 1st Int. Topl. Mtg. High Temperature Reactor Technology, Petten, The Netherlands, April 22-24, 2002, International Atomic Energy Agency (2002).
    • (2002) Proc. 1st Int. Topl. Mtg. High Temperature Reactor Technology
    • Miller, G.K.1    Petti, D.A.2    Maki, J.T.3
  • 27
    • 0036706551 scopus 로고    scopus 로고
    • Long time experience with the development of HTR fuel elements in Germany
    • H. NICKEL et al., "Long Time Experience with the Development of HTR Fuel Elements in Germany," Nucl. Eng. Des., 217, 141 (2002).
    • (2002) Nucl. Eng. Des. , vol.217 , pp. 141
    • Nickel, H.1
  • 28
    • 33745515894 scopus 로고    scopus 로고
    • Key differences in the fabrication of U.S. and German TRISO-coated particle fuel, and their implications on fuel performances
    • Petten, The Netherlands, April 22-24, 2002, International Atomic Energy Agency
    • D. A. PETTI, J. BUONGIORNO, J. T. MAKI, and G. K. MILLER, "Key Differences in the Fabrication of U.S. and German TRISO-Coated Particle Fuel, and Their Implications on Fuel Performances," Proc. 1st Int. Topl. Mtg. High Temperature Reactor Technology, Petten, The Netherlands, April 22-24, 2002, International Atomic Energy Agency (2002).
    • (2002) Proc. 1st Int. Topl. Mtg. High Temperature Reactor Technology
    • Petti, D.A.1    Buongiorno, J.2    Maki, J.T.3    Miller, G.K.4
  • 29
    • 33745577445 scopus 로고    scopus 로고
    • Mathematical model and computer code for coated particles performance at normal operating conditions
    • Petten, The Netherlands, April 22-24, 2002, International Atomic Energy Agency
    • I. GOLUBEV, I. KADARMETOV, and V. MAKAROV, "Mathematical Model and Computer Code for Coated Particles Performance at Normal Operating Conditions," Proc. 1st Int. Topl. Mtg. High Temperature Reactor Technology, Petten, The Netherlands, April 22-24, 2002, International Atomic Energy Agency (2002).
    • (2002) Proc. 1st Int. Topl. Mtg. High Temperature Reactor Technology
    • Golubev, I.1    Kadarmetov, I.2    Makarov, V.3
  • 30
    • 0035079601 scopus 로고    scopus 로고
    • Coated particle fuel to improve safety, design, and economics in water-cooled and gas-cooled reactors
    • J. PORTA et al., "Coated Particle Fuel to Improve Safety, Design, and Economics in Water-Cooled and Gas-Cooled Reactors," Prog. Nucl. Energy, 38, 407 (2001).
    • (2001) Prog. Nucl. Energy , vol.38 , pp. 407
    • Porta, J.1
  • 31
    • 0035358402 scopus 로고    scopus 로고
    • Prediction of fuel performance and fission gas release behavior during normal operation of the high temperature engineering test reactor by JAERI and FZJ modeling approach
    • K. SAWA et al., " Prediction of Fuel Performance and Fission Gas Release Behavior During Normal Operation of the High Temperature Engineering Test Reactor by JAERI and FZJ Modeling Approach," J. Nucl. Sci. Technol., 38, 6, 411 (2001).
    • (2001) J. Nucl. Sci. Technol. , vol.38 , Issue.6 , pp. 411
    • Sawa, K.1
  • 32
    • 0035438450 scopus 로고    scopus 로고
    • Safety criteria and quality control of HTTR fuel
    • K. SAWA, S. SUZUKI, and S. SHIOZAWA, "Safety Criteria and Quality Control of HTTR Fuel," Nucl. Eng. Des., 208, 305 (2001).
    • (2001) Nucl. Eng. Des. , vol.208 , pp. 305
    • Sawa, K.1    Suzuki, S.2    Shiozawa, S.3
  • 33
    • 0035366610 scopus 로고    scopus 로고
    • Consideration of the effects on fuel particle behavior from shrinkage cracks in the inner pyrocarbon layer
    • 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 (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
  • 34
    • 0035081665 scopus 로고    scopus 로고
    • Requirements for high temperature reactor fuel particle design assessment
    • P. CHAPELOT et al., "Requirements for High Temperature Reactor Fuel Particle Design Assessment," Prog. Nucl. Energy, 38, 3, 415 (2001).
    • (2001) Prog. Nucl. Energy , vol.38 , Issue.3 , pp. 415
    • Chapelot, P.1
  • 35
    • 0033688557 scopus 로고    scopus 로고
    • Fission product release behavior of individual coated fuel particles for high-temperature gas-cooled reactors
    • K. MINATO, K. SAWA, T. KOYA, T. TOMITA, A. ISHIKAWA, C. A. BALDWIN, W. A. GABBARD, and C. M. MALONE, "Fission Product Release Behavior of Individual Coated Fuel Particles for High-Temperature Gas-Cooled Reactors," Nucl. Technol., 131, 36 (2000).
    • (2000) Nucl. Technol. , vol.131 , pp. 36
    • Minato, K.1    Sawa, K.2    Koya, T.3    Tomita, T.4    Ishikawa, A.5    Baldwin, C.A.6    Gabbard, W.A.7    Malone, C.M.8
  • 36
    • 0029343152 scopus 로고
    • Irradiation behavior of HTGR coated particle fuel at abnormally high temperature
    • K. FUKUDA, S. KASHIMURA, T. TOBITA, and T. KIKUCHI, "Irradiation Behavior of HTGR Coated Particle Fuel at Abnormally High Temperature," Nucl. Eng. Des., 157, 221 (1995).
    • (1995) Nucl. Eng. Des. , vol.157 , pp. 221
    • Fukuda, K.1    Kashimura, S.2    Tobita, T.3    Kikuchi, T.4
  • 37
    • 0027608220 scopus 로고
    • Release behavior of metallic fission products from HTGR fuel particles at 1600 and 1900°C
    • K. MINATO et al., "Release Behavior of Metallic Fission Products from HTGR Fuel Particles at 1600 and 1900°C," J. Nucl. Mater., 202, 47 (1993).
    • (1993) J. Nucl. Mater. , vol.202 , pp. 47
    • Minato, K.1
  • 38
  • 39
    • 0024303932 scopus 로고
    • The performance of high-temperature reactor fuel particles at extreme temperatures
    • H. NABIELEK, W. SCHENK, W. HEIT, A. W. MEHNER, and D. T. GOODIN, "The Performance of High-Temperature Reactor Fuel Particles at Extreme Temperatures," Nucl. Technol., 84, 62 (1989).
    • (1989) Nucl. Technol. , vol.84 , pp. 62
    • Nabielek, H.1    Schenk, W.2    Heit, W.3    Mehner, A.W.4    Goodin, D.T.5
  • 40
    • 0034207748 scopus 로고    scopus 로고
    • Retention of fission product cesium in ZrC-coated fuel particles for high-temperature gas-cooled reactors
    • K. MINATO et al., "Retention of Fission Product Cesium in ZrC-Coated Fuel Particles for High-Temperature Gas-Cooled Reactors," J. Nucl. Mater., 279, 181 (2000).
    • (2000) J. Nucl. Mater. , vol.279 , pp. 181
    • Minato, K.1
  • 41
    • 0003183797 scopus 로고    scopus 로고
    • Irradiation experiment on ZrC-coated fuel particles for high-temperature gas-cooled reactors
    • K. MINATO, T. OGAWA, K. SAWA, A. ISHIKAWA, T. TOMITA, S. IIDA, and H. SEKINO, "Irradiation Experiment on ZrC-Coated Fuel Particles for High-Temperature Gas-Cooled Reactors," Nucl. Technol., 130, 272 (2000).
    • (2000) Nucl. Technol. , vol.130 , pp. 272
    • Minato, K.1    Ogawa, T.2    Sawa, K.3    Ishikawa, A.4    Tomita, T.5    Iida, S.6    Sekino, H.7
  • 42
    • 0031646220 scopus 로고    scopus 로고
    • Deterioration of ZrC-coated fuel particle caused by failure of pyrolitic carbon layer
    • K. MINATO et al., "Deterioration of ZrC-Coated Fuel Particle Caused by Failure of Pyrolitic Carbon Layer," J. Nucl. Mater., 252, 13 (1998).
    • (1998) J. Nucl. Mater. , vol.252 , pp. 13
    • Minato, K.1
  • 43
    • 0031250914 scopus 로고    scopus 로고
    • Fission product release from Zr-coated fuel particles during post-irradiation heating at 1800 and 2000°C
    • K. MINATO, T. OGAWA, K. FUKUDA, H. SEKINO, I. KITAGAWA, and N. MITA, "Fission Product Release from Zr-Coated Fuel Particles During Post-Irradiation Heating at 1800 and 2000°C," J. Nucl. Mater., 249, 142 (1997).
    • (1997) J. Nucl. Mater. , vol.249 , pp. 142
    • Minato, K.1    Ogawa, T.2    Fukuda, K.3    Sekino, H.4    Kitagawa, I.5    Mita, N.6
  • 45
    • 4444243210 scopus 로고    scopus 로고
    • Use of plutonium in pebble bed HTGRs
    • Beijing, China, November 2-4, 1998, IAEA-TECDOC-1210, International Atomic Energy Agency
    • K. KUGELER, W. VON LENSA, G. HAAG, and H. J. RÜTTEN, "Use of Plutonium in Pebble Bed HTGRs," Proc. Int. Working Group on Gas-Cooled Reactors Mtg., Beijing, China, November 2-4, 1998, IAEA-TECDOC-1210, p. 229, International Atomic Energy Agency (1998).
    • (1998) Proc. Int. Working Group on Gas-cooled Reactors Mtg. , pp. 229
    • Kugeler, K.1    Von Lensa, W.2    Haag, G.3    Rütten, H.J.4
  • 48
    • 4444374077 scopus 로고
    • Generation and benchmarking of a 69 group cross section library for thermal reactor applications
    • J. J. KIM, J. T. LEE, and H. R. KIM, "Generation and Benchmarking of a 69 Group Cross Section Library for Thermal Reactor Applications," J. Korean Nucl. Soc., 21, 245 (1989).
    • (1989) J. Korean Nucl. Soc. , vol.21 , pp. 245
    • Kim, J.J.1    Lee, J.T.2    Kim, H.R.3


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