-
1
-
-
0032634719
-
High burnup effects on fuel behaviour under accident conditions: The tests CABRI REP-Na
-
F. SCHMITZ and J. PAPIN, "High Burnup Effects on Fuel Behaviour under Accident Conditions: The Tests CABRI REP-Na," J. Nucl. Mat. 270, pp 55-64 (1999).
-
(1999)
J. Nucl. Mat.
, vol.270
, pp. 55-64
-
-
Schmitz, F.1
Papin, J.2
-
2
-
-
0036602994
-
High-burnup BWR fuel behavior under simulated reactivity-initiated accident conditions
-
T. NAKAMURA, K. KUSAGAYA, T. FUKETA and H. UETSUKA, "High-Burnup BWR Fuel Behavior under Simulated Reactivity-Initiated Accident Conditions," Nucl. Technology, 138, pp 246-259 (2002).
-
(2002)
Nucl. Technology
, vol.138
, pp. 246-259
-
-
Nakamura, T.1
Kusagaya, K.2
Fuketa, T.3
Uetsuka, H.4
-
3
-
-
32044433181
-
SIMULATE-3K: Models & methodology
-
SIMULATE-3K, Rev 0, Studsvik Scandpower
-
SIMULATE-3K, "SIMULATE-3K: Models & Methodology," Report SOA-98/13, Rev 0, Studsvik Scandpower (1998).
-
(1998)
Report SOA-98/13
-
-
-
4
-
-
32044464620
-
Status of development of the SCANAIR code for the description of fuel behavior under reactivity initiated accidents
-
Park City, Utah, USA, April 10-13
-
E. FEDERICI, F. LAMARE, V. BESSIRON and J. PAPIN, "Status of Development of the SCANAIR Code for the Description of Fuel Behavior under Reactivity Initiated Accidents," Proc. of the 2000 Int. Topical Meeting on LWR Fuel Performance, Park City, Utah, USA, April 10-13, (2000).
-
(2000)
Proc. of the 2000 Int. Topical Meeting on LWR Fuel Performance
-
-
Federici, E.1
Lamare, F.2
Bessiron, V.3
Papin, J.4
-
5
-
-
32044459163
-
FRAPCON-3: A computer code for the calculation of steady-state, thermal-mechanical behavior of oxide fuel rods for high burnup
-
G.A. BERNA, C.E. BEYER, K.L. DAVIS and D.D. LANNING, "FRAPCON-3: A Computer Code for the Calculation of Steady-State, Thermal-Mechanical Behavior of Oxide Fuel Rods for High Burnup," NUREG Report NUREG/CR-6534, Volume 2 (1997).
-
(1997)
NUREG Report
, vol.2 NUREG-CR-6534
-
-
Berna, G.A.1
Beyer, C.E.2
Davis, K.L.3
Lanning, D.D.4
-
6
-
-
32044443281
-
Thermohydraulic relationships for advanced water cooled reactors
-
International Atomic Energy Agency
-
IAEA, "Thermohydraulic Relationships for Advanced Water Cooled Reactors," IAEA-TECDOC-1203, International Atomic Energy Agency, (2001).
-
(2001)
IAEA-TECDOC-1203
-
-
-
7
-
-
0032309150
-
Cladding metallurgy and fracture behavior during reactivity-initiated accidents at high burnup
-
H.M. CHUNG and T.F. KASSNER, "Cladding Metallurgy and Fracture Behavior during Reactivity-Initiated Accidents at High Burnup," Nucl. Engng. Design, 186, pp 411-427 (1998).
-
(1998)
Nucl. Engng. Design
, vol.186
, pp. 411-427
-
-
Chung, H.M.1
Kassner, T.F.2
-
8
-
-
85168662828
-
Deformation and fracture properties of neutron-irradiated recrystallized zircaloy-2 cladding under uniaxial tension
-
R.B. Adamson and L.F.P. van Swam (eds)
-
th Int. Symp. ASTM STP-939, R.B. Adamson and L.F.P. van Swam (eds), pp 737-747 (1987).
-
(1987)
th Int. Symp. ASTM STP-939
, pp. 737-747
-
-
Yasuda, T.1
Nakatsuka, M.2
Yamashita, K.3
-
11
-
-
0003214865
-
Behavior of PWR and BWR fuels during reactivity-initiated accident conditions
-
Park City, Utah, USA, April 10-13
-
T. FUKETA, T. NAKAMURA, H. SASAJIMA, F. NAGASE, H. UETSUKA, K. KIKUCHI and T. ABE, "Behavior of PWR and BWR Fuels during Reactivity-Initiated Accident Conditions," Proc. of the 2000 Int. Topical Meeting on LWR Fuel Performance, Park City, Utah, USA, April 10-13, (2000).
-
(2000)
Proc. of the 2000 Int. Topical Meeting on LWR Fuel Performance
-
-
Fuketa, T.1
Nakamura, T.2
Sasajima, H.3
Nagase, F.4
Uetsuka, H.5
Kikuchi, K.6
Abe, T.7
-
12
-
-
0342819182
-
Effects of irradiation and hydriding on the mechanical properties of zircaloy-4 at high fluence
-
L.F.P. van Swam and C.M. Eucken (eds)
-
th Int. Symp. ASTM STP-1023, L.F.P. van Swam and C.M. Eucken (eds), pp 548-569 (1989).
-
(1989)
th Int. Symp. ASTM STP-1023
, pp. 548-569
-
-
Garde, A.M.1
-
13
-
-
5544310313
-
Effects of hydride precipitate localization and neutron fluence on the ductility of irradiated zircaloy-4
-
E.R. Bradley and G..P. Sabol (eds)
-
th Int. Symp. ASTM STP-1295, E.R. Bradley and G..P. Sabol (eds), pp 407-430 (1996).
-
(1996)
th Int. Symp. ASTM STP-1295
, pp. 407-430
-
-
Garde, A.M.1
Smith, G.P.2
Pirek, R.C.3
-
14
-
-
32044469731
-
A strain-based clad failure criterion for reactivity initiated accidents in light water reactors
-
Quantum Technologies AB
-
L.O. JERNKVIST, A.R. MASSIH and P. RUDLING, "A Strain-Based Clad Failure Criterion for Reactivity Initiated Accidents in Light Water Reactors," Report TR 03-008, Quantum Technologies AB (2003). Available via internet at www.quantumtech.se.
-
(2003)
Report TR
, vol.3
, Issue.8
-
-
Jernkvist, L.O.1
Massih, A.R.2
Rudling, P.3
-
16
-
-
33745346015
-
Pulse width in a rod ejection accident
-
Aix-en-Provence, France, May 13-15
-
D.J. DIAMOND, B.P. BROMLEY and A.L. ARONSON, "Pulse Width in a Rod Ejection Accident," Proc. of the NEA CSNI Topical Meeting on RIA Fuel Safety Criteria, Aix-en-Provence, France, May 13-15, (2002).
-
(2002)
Proc. of the NEA CSNI Topical Meeting on RIA Fuel Safety Criteria
-
-
Diamond, D.J.1
Bromley, B.P.2
Aronson, A.L.3
-
17
-
-
32044442829
-
Three dimensional analysis of RIA in PWR and BWR with high burnup fuel
-
Tokai, Japan, March 4-5
-
T. NAKAJIMA, I. KOMATSU and R. YOSHIKI, "Three Dimensional Analysis of RIA in PWR and BWR with High Burnup Fuel," Proc. of the Fuel Safety Research Specialist's Meeting, Tokai, Japan, March 4-5, (2002).
-
(2002)
Proc. of the Fuel Safety Research Specialist's Meeting
-
-
Nakajima, T.1
Komatsu, I.2
Yoshiki, R.3
-
18
-
-
32044435016
-
Fuel failure risk assessment under rod ejection accident in PWR's using the RIA simulation tests database - The French utility position
-
Portland, Oregon, USA, March 2-6
-
S. STELLETTA and N. WAECKEL, "Fuel Failure Risk Assessment under Rod Ejection Accident in PWR's Using the RIA Simulation Tests Database - the French Utility Position," Proc. of the 1997 Int. Topical Meeting on LWR Fuel Performance, Portland, Oregon, USA, March 2-6, pp 721-728 (1997).
-
(1997)
Proc. of the 1997 Int. Topical Meeting on LWR Fuel Performance
, pp. 721-728
-
-
Stelletta, S.1
Waeckel, N.2
-
19
-
-
30644478180
-
A cladding failure model for fuel rods subjected to operational and accident transients
-
Windermere, UK, June 19-23
-
Y.R. RASHID, R.O. MONTGOMERY, W.F. LYON and R. YANG, "A Cladding Failure Model for Fuel Rods Subjected to Operational and Accident Transients," Proc. of the IAEA Technical Committee Meeting on Nuclear Fuel Behaviour Modelling at High Burnup and its Experimental Support, Windermere, UK, June 19-23, (2000).
-
(2000)
Proc. of the IAEA Technical Committee Meeting on Nuclear Fuel Behaviour Modelling at High Burnup and Its Experimental Support
-
-
Rashid, Y.R.1
Montgomery, R.O.2
Lyon, W.F.3
Yang, R.4
-
20
-
-
32044453206
-
Revised reactivity initiated accident acceptance criteria for high burnup fuel
-
Wurzburg, Germany, March 16-19
-
R. YANG, R.O. MONTGOMERY and N. WAECKEL "Revised Reactivity Initiated Accident Acceptance Criteria for High Burnup Fuel," Proc. European Nuclear Society ENS TopFuel-2003 Conference, Wurzburg, Germany, March 16-19 (2003).
-
(2003)
Proc. European Nuclear Society ENS TopFuel-2003 Conference
-
-
Yang, R.1
Montgomery, R.O.2
Waeckel, N.3
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