OXIDE FUEL TRANSIENTS

[1] BLANK H, 1983, RES MECH, V5, P121

[2] BLANK H, 1988, P JAHRESTAGUNG KERNT, P433

[3] COQUERELLE M, 1987, WATER REACTOR FUEL B, P163

[4] COQUERELLE M, 1984, J PHYSIQUE, V45, pC2

[5] CALCULATIONAL METHODS FOR DIFFUSIONAL GAS-RELEASE [J]. NUCLEAR ENGINEERING AND DESIGN, 1987, 101 (03) : 259 - 265

[6] OXYGEN POTENTIAL MEASUREMENTS IN IRRADIATED MIXED-OXIDE FUEL [J]. JOURNAL OF NUCLEAR MATERIALS, 1984, 124 : 44 - 55

[7] HOH A, 1973, NUCL INSTRUM METHODS, V114, P459

[8] URANUS - COMPUTER-PROGRAM FOR THERMAL AND MECHANICAL ANALYSIS OF FUEL RODS IN A NUCLEAR-REACTOR [J]. NUCLEAR ENGINEERING AND DESIGN, 1978, 45 (02) : 325 - 342

[9] LASSMANN K, 1989, J NUCL MATER, V166, P109

[10] DIFFUSION-PROCESSES AND SURFACE EFFECTS IN NON-STOICHIOMETRIC NUCLEAR-FUEL OXIDES UO2+X AND (U, PU)O2+/-X [J]. JOURNAL OF NUCLEAR MATERIALS, 1983, 114 (2-3) : 121 - 135

[1] BLANK H, 1983, RES MECH, V5, P121

[2] BLANK H, 1988, P JAHRESTAGUNG KERNT, P433

[3] COQUERELLE M, 1987, WATER REACTOR FUEL B, P163

[4] COQUERELLE M, 1984, J PHYSIQUE, V45, pC2

[5] CALCULATIONAL METHODS FOR DIFFUSIONAL GAS-RELEASE [J]. NUCLEAR ENGINEERING AND DESIGN, 1987, 101 (03) : 259 - 265

[6] OXYGEN POTENTIAL MEASUREMENTS IN IRRADIATED MIXED-OXIDE FUEL [J]. JOURNAL OF NUCLEAR MATERIALS, 1984, 124 : 44 - 55

[7] HOH A, 1973, NUCL INSTRUM METHODS, V114, P459

[8] URANUS - COMPUTER-PROGRAM FOR THERMAL AND MECHANICAL ANALYSIS OF FUEL RODS IN A NUCLEAR-REACTOR [J]. NUCLEAR ENGINEERING AND DESIGN, 1978, 45 (02) : 325 - 342

[9] LASSMANN K, 1989, J NUCL MATER, V166, P109

[10] DIFFUSION-PROCESSES AND SURFACE EFFECTS IN NON-STOICHIOMETRIC NUCLEAR-FUEL OXIDES UO2+X AND (U, PU)O2+/-X [J]. JOURNAL OF NUCLEAR MATERIALS, 1983, 114 (2-3) : 121 - 135