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1
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0030252274
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"French Studies on High-Burn-up Fuel Transient Behavior Under RIA Conditions"
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J. PAPIN et al., "French Studies on High-Burn-up Fuel Transient Behavior Under RIA Conditions," Nucl. Safety, 37, 289 (1996).
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(1996)
Nucl. Safety
, vol.37
, pp. 289
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Papin, J.1
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2
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0032634719
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"High Burn-Up Effects on Fuel Behavior Under Accident Conditions: The Tests CABRI REP-Na"
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F. SCHMITZ and J. PAPIN, "High Burn-Up Effects on Fuel Behavior Under Accident Conditions: The Tests CABRI REP-Na," J. Nucl. Mater., 270, 55 (1999).
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(1999)
J. Nucl. Mater.
, vol.270
, pp. 55
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-
Schmitz, F.1
Papin, J.2
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3
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33947516099
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"Further Results and Analysis of MOX Fuel Behavior Under Reactivity Accident Conditions in CABRI"
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presented at Bethesda, Maryland, October
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J. PAPIN, F. SCHMITZ, and B. CAZALIS, "Further Results and Analysis of MOX Fuel Behavior Under Reactivity Accident Conditions in CABRI," presented at 27th WRSM, Bethesda, Maryland, October 1999.
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(1999)
27th WRSM
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Papin, J.1
Schmitz, F.2
Cazalis, B.3
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4
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33947502698
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"SURA: A Test Facility to Investigate the Safety of LMFBR and PWR Fuels"
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presented at Lisbon, Portugal
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C. MARQUTE et al., "SURA: A Test Facility to Investigate the Safety of LMFBR and PWR Fuels," presented at Int. Symp. Research Reactor Utilization, Lisbon, Portugal, 1999.
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(1999)
Int. Symp. Research Reactor Utilization
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Marqute, C.1
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5
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32044464620
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"The SCANAIR Code for Description of Fuel Behaviour Under Reactivity Initiated Accident"
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presented at Park City, Utah, April 10-13
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E. FÉDÉRICI, F. LAMARE, V. BESSIRON, and J. PAPIN, "The SCANAIR Code for Description of Fuel Behaviour Under Reactivity Initiated Accident," presented at Int. Topl. Mtg. Light Water Reactor Fuel Performance, Park City, Utah, April 10-13, 2000.
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(2000)
Int. Topl. Mtg. Light Water Reactor Fuel Performance
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Fédérici, E.1
Lamare, F.2
Bessiron, V.3
Papin, J.4
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6
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33750387633
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"The SCANAIR Code Version 3.2: Main Futures and Status of Qualification"
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presented at Halden, Norway, September
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E. FÉDÉRICI, F. LAMARE, V. BESSIRON, and J. PAPIN, "The SCANAIR Code Version 3.2: Main Futures and Status of Qualification," presented at IAEA Technical Committee Mtg. Fuel Behavior Under Transient and LOCA Conditions, Halden, Norway, September 2001.
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(2001)
IAEA Technical Committee Mtg. Fuel Behavior Under Transient and LOCA Conditions
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Fédérici, E.1
Lamare, F.2
Bessiron, V.3
Papin, J.4
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7
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32044472610
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"The PROMETRA Programme: Assessment of Mechanical Properties of Zircaloy-4 Cladding During an RIA"
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M. BALOURDET, C. BERNAUDAT, V. BASINI, and N. HOURDEQUIN, "The PROMETRA Programme: Assessment of Mechanical Properties of Zircaloy-4 Cladding During an RIA," Proc. SMIRT 15, Vol. II, p. 485 (1999).
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(1999)
Proc. SMIRT 15
, vol.2
, pp. 485
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Balourdet, M.1
Bernaudat, C.2
Basini, V.3
Hourdequin, N.4
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8
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44949125284
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"Zircaloy-4 Cladding Mechanical Behavior in the Field of RIA Transients Through the PROMETRA Program"
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presented at Stockholm, Sweden, June
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J. DESQUINES, B. CAZALIS. C. BERNAUDAT, C. POUSSARD, X. AVERTY, and P. YVON, "Zircaloy-4 Cladding Mechanical Behavior in the Field of RIA Transients Through the PROMETRA Program," presented at ASTM Conf. Zirconium in the Nuclear Industry, Stockholm, Sweden, June 2004.
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(2004)
ASTM Conf. Zirconium in the Nuclear Industry
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Desquines, J.1
Cazalis, B.2
Bernaudat, C.3
Poussard, C.4
Averty, X.5
Yvon, P.6
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9
-
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33947505756
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"The PROMETRA Program: A Reliable Material Data Base for Highly Irradiated Zircaloy-4, Zirlo™, M5™ Fuel Claddings"
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presented at Beijing, China, August
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B. CAZALIS, J. DESQUINES, C. BERNAUDAT, C. POUSSARD, X. AVERTY, and P. YVON, "The PROMETRA Program: A Reliable Material Data Base for Highly Irradiated Zircaloy-4, Zirlo™, M5™ Fuel Claddings," presented at SMIRT 18, Beijing, China, August 2005.
-
(2005)
SMIRT 18
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Cazalis, B.1
Desquines, J.2
Bernaudat, C.3
Poussard, C.4
Averty, X.5
Yvon, P.6
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10
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33947528600
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"The PROMETRA Program: Fuel Cladding Mechanical Behavior Under High Strain Rate"
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B. CAZALIS, J. DESQUINES, C. POUSSARD, M. PETIT, Y. MONERIE, C. BERNAUDAT, P. YVON, and X. AVERTY, "The PROMETRA Program: Fuel Cladding Mechanical Behavior Under High Strain Rate," Nucl. Technol, 157, 215 (2007).
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(2007)
Nucl. Technol
, vol.157
, pp. 215
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Cazalis, B.1
Desquines, J.2
Poussard, C.3
Petit, M.4
Monerie, Y.5
Bernaudat, C.6
Yvon, P.7
Averty, X.8
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11
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33947497992
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"Main Outcomes from the PATRICIA Program on Clad to Coolant Heat Transfer During RIAs"
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presented at Washington, D.C., October
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V. BESSIRON, "Main Outcomes from the PATRICIA Program on Clad to Coolant Heat Transfer During RIAs," presented at NSRC 2002, Washington, D.C., October 2002.
-
(2002)
NSRC 2002
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Bessiron, V.1
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12
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33947535580
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"Modeling of Clad to Coolant Heat Transfer for RIA Application"
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submitted to
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V. BESSIRON, "Modeling of Clad to Coolant Heat Transfer for RIA Application," submitted to J. Nucl. Sci. Technol.
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J. Nucl. Sci. Technol.
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Bessiron, V.1
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13
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33947541012
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"In Pile and Out-of-Pile Burst Release of Fission Gases"
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presented at Stonsfjell, Norway, September
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Y. GUÉRIN, "In Pile and Out-of-Pile Burst Release of Fission Gases," presented at EHPG Mtg., Stonsfjell, Norway, September 2002.
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(2002)
EHPG Mtg.
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Guérin, Y.1
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15
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33750404612
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"The Role of Grain Boundary Fission Gases in High Burn-Up Fuel Under Reactivity Initiated Accident"
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presented at Cadarache, France, September 26-29
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F. LEMOINE, J. PAPIN, J-M. FRIZONNET, B, CAZALIS, and H. RIGAT, "The Role of Grain Boundary Fission Gases in High Burn-Up Fuel Under Reactivity Initiated Accident," presented at Int. Topl. Mtg. Fission Gas Behaviour in Water Reactor Fuel, Cadarache, France, September 26-29, 2000.
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(2000)
Int. Topl. Mtg. Fission Gas Behaviour in Water Reactor Fuel
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Lemoine, F.1
Papin, J.2
Frizonnet, J.-M.3
Cazalis, B.4
Rigat, H.5
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16
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0031234810
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"High Burn-Up Fuel Behavior Related to Fission Gas Effects Under Reactivity Initiated Accidents (RIA) Conditions"
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F. LEMOINE, "High Burn-Up Fuel Behavior Related to Fission Gas Effects Under Reactivity Initiated Accidents (RIA) Conditions," J. Nucl. Mater., 248, 238 (1997).
-
(1997)
J. Nucl. Mater.
, vol.248
, pp. 238
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Lemoine, F.1
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17
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84885311777
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"Estimation of the Grain Boundary Gas Inventory in MIMAS/AUC MOX Fuel and Consistency with REP-Na Test Results"
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presented at Kyoto, Japan, October
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F. LEMOINE, "Estimation of the Grain Boundary Gas Inventory in MIMAS/AUC MOX Fuel and Consistency with REP-Na Test Results," presented at Water Reactor Fuel Performance Mtg., Kyoto, Japan, October 2005.
-
(2005)
Water Reactor Fuel Performance Mtg.
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Lemoine, F.1
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19
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33947542859
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"The Fracture and Spallation of Zirconia Layers in High Burn-Up PWR Cladding Submitted to RIA Transients"
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presented at Beijing, China, August
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J. DESQUINES, V. GEORGENTHUM, F. LEMOINE, and B. CAZALIS, "The Fracture and Spallation of Zirconia Layers in High Burn-Up PWR Cladding Submitted to RIA Transients," presented at SMIRT 18, Beijing, China, August 2005.
-
(2005)
SMIRT 18
-
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Desquines, J.1
Georgenthum, V.2
Lemoine, F.3
Cazalis, B.4
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20
-
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33947514083
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"Study and Modelling of Zirconia Cracking and Spalling in High Burn-Up PWR Fuel Claddings Submitted to RIA Transients"
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presented at Kyoto. Japan, October
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V. GEORGENTHUM, J. DESQUINES, and R. ARNAUD, "Study and Modelling of Zirconia Cracking and Spalling in High Burn-Up PWR Fuel Cladding, Submitted to RIA Transients." presented at Water Reactor Fuel Performance Mtg., Kyoto. Japan, October 2005.
-
(2005)
Water Reactor Fuel Performance Mtg.
-
-
Georgenthum, V.1
Desquines, J.2
Arnaud, R.3
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21
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33750409300
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"The Role of Fission Gases on the High Burn-Up Fuel Behaviour in Reactivity Initiated Accident Conditions"
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presented at Halifax,, Canada, August
-
F. LEMOINE, B. CAZALIS, and H. RIGAT, "The Role of Fission Gases on the High Burn-Up Fuel Behaviour in Reactivity Initiated Accident Conditions," presented at 10th Int. Symp. Thermodynamics of Nuclear Materials, Halifax,, Canada, August 2000.
-
(2000)
10th Int. Symp. Thermodynamics of Nuclear Materials
-
-
Lemoine, F.1
Cazalis, B.2
Rigat, H.3
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22
-
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0003214865
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"Behavior of High Burn-Up PWR and BWR Fuels During Reactivity Initiated Accident Conditions"
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presented at Park City, Utah, April 10-13
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T. FUKETA, T. NAKAMURA, H. SASAJIMA, F. NAGASE, and H. UETSUKA, "Behavior of High Burn-Up PWR and BWR Fuels During Reactivity Initiated Accident Conditions," presented at Int. Topl. Mig. Light Water Reactor Fuel Performance, Park City, Utah, April 10-13, 2000.
-
(2000)
Int. Topl. Mtg. Light Water Reactor Fuel Performance
-
-
Fuketa, T.1
Nakamura, T.2
Sasajima, H.3
Nagase, F.4
Uetsuka, H.5
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23
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33947538379
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"Interim Staff Guidance 11, Rev. 3"
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ISG-11, U.S. Nuclear Regulatory Commission
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"Interim Staff Guidance 11, Rev. 3," ISG-11, U.S. Nuclear Regulatory Commission (2003).
-
(2003)
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-
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24
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33947540449
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"EPRI Perspective on Fuel Reconfiguration"
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presented at Argonne, Illinois, August
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A. MACHIELS, "EPRI Perspective on Fuel Reconfiguration," presented at SNF Dry Cask Storage and Transportation Mtg., Argonne, Illinois, August 2004.
-
(2004)
SNF Dry Cask Storage and Transportation Mtg.
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Machiels, A.1
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25
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14744279559
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"Understanding Hydride- and Hydrogen-Related Process in High-Burn-Up Cladding in Spent-Fuel-Storage and Accident Situations"
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Orlando, Florida, September 2004
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H. M. CHUNG, "Understanding Hydride- and Hydrogen-Related Process in High-Burn-Up Cladding in Spent-Fuel-Storage and Accident Situations," Proc. Int. Mtg. LWR Fuel Performance, Orlando, Florida, September 2004 (2004).
-
(2004)
Proc. Int. Mtg. LWR Fuel Performance
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Chung, H.M.1
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26
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14744281678
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"Evaluation of Irradiation Effect on Spent Fuel Cladding Creep Properties"
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Orlando, Florida, September 2004
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K. ITO, K. KAMIMURA, and Y. TSUKUDA, "Evaluation of Irradiation Effect on Spent Fuel Cladding Creep Properties," Proc. Int. Mtg. LWR Fuel Performance, Orlando, Florida, September 2004 (2004).
-
(2004)
Proc. Int. Mtg. LWR Fuel Performance
-
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Ito, K.1
Kamimura, K.2
Tsukuda, Y.3
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