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STP939-EB/Sep. 1987
Subject Index
A
Accelerating kinetics, 189 Activation energy, apparent
recovery, 567-568 recrystallization, 575
Active slip systems, 635 Alloying
additions, irradiation growth ef- fects, 73-78
delayed hydride cracking effects, 231-232
Alloys, 86, 101, 120 Alpha grains, 325, 330-331 Anisotropic parameters, correlation
with reduction parameter, 656
Anisotropy, 101, 120, 631 ball rolling, 30 definition, 24 early work, 25 optical properties, 32 theory, 26-27 tube reducing, 30 tubing, 30 types, 24-25 Zircaloy, 23-33 Zircaloy-4 effects, 557-558 Zircaloy-4 strips, 114-115 see also Cold reduction, anisotropy
effect; Pole figures; Preferred orientation
Annealing, 663 after final cold-working, 425-426 parameters, 367,441-442 temperature effect before quench-
ing, 423,425 temperature effect on Zircaloy-4
thin strips, 667, 670-671 upper t~-range after B-quenching,
425
Aqueous corrosion resistance and chemical inhomo-
geneity size, 762, 766, 768- 770
weight gain versus probability of occurrence, 768-769
Zircaloy, 769 ASTM B 353, 29-30, 750 ASTM E 399, 581,583 ASTM E 813,584, 588 ASTM G 2,208, 244, 251,257,269,
367, 431,434 Atomic-diffusion coefficient, 16 Autoclave test, 243-256, 294, 364,
367 comparison of temperature re-
sponse, standard heat-treated tubing, 253
frequency distribution of weight gains in single and multiple tests, 245
limitations, 255 parametric test series, 244, 246-
249 autoclave loading, 248-249 nodule coverage, 244, 246 pressure, 247 refreshment, 248 temperature, 246-247 time, 247
round-robin test Series, 249-251 survey, 244-245 weight gains, 333
versus nodule rating, 252 Zircaloy-2, final annealing tem-
perature effect, 324
B
Ball rolling, 30
807
Copyrighr ~ 1987 b y A S T M International www.astm.org
808 ZIRCONIUM IN THE NUCLEAR INDUSTRY: SEVENTH SYMPOSIUM
Ball swaging, 30 Bar quenching, comparison with bil
let quenching, 358 Basketweave structure, 284-285, 291 Basquin's law, 602 Bauschinger effect, 647-648 Bending, Zircaloy-4 cladding tube
a-phase, 471 deformed under azimuthal tem
perature difference and cooling, 472
/3-phase cladding oxidation, 506 decomposition, 94-95 disappearance, 521, 523 irregular penetration, 174, 176
|3-quenching, 28, 101, 284, 292, 305, 341-362
accumulation of temperature effects after, 426
aggressive in-process, 362 alloy chemistry effects, 359 annealing in upper a-range, 425 billet quench, 344, 346, 349-350,
352-353 comparison of billet and bar, 358 experimental procedure, 343 hollow, 337, 351, 354, 359, 362 in-process, 357-359 microstructure, 371, 373
corrosion relationships, 360-362
Zircaloy-2, 308-311 Zircaloy clad produced by re-
crystallization annealing, 343-347
rates, 307 steam autoclave corrosion, 351,
357 temperature effect, 288-289 Zircaloy-2 and 4 differences, 359-
360 |3-treatment, 168 Biaxial creep, creep loci and, 121,
123 Biaxial deformation, 120 Billet quenching
|3-quenching, 344, 346, 349-350, 352-353
comparison with bar quenching, 358
Zircaloy-4, 434, 437 Boiling water reactor, 206-207, 243,
292, 307, 321, 341, 364, 387-388, 417-418, 419, 679, 734
cladding, 675 loss-of-coolant accident, 452 nodular corrosion, 257-258 spacer effect on nodular oxidation
of Zircaloy, 212-213 Brittle behavior
crack morphologies, 784-785 fracture site, expanding mandrel
tests, 790-791, 793-795 fracture surface morphologies,
776, 782-783, 786 zirconium alloy pressure tubes,
584-588 Burnup, nodular corrosion effect,
420 Burst pressure, versus normalized
annealing time, 444 Burst strain
versus azimuthal temperature difference, Zircaloy-4 cladding tubes, 470, 473, 481
versus burst temperature, Zircaloy-4 cladding tubes, 469, 482
initial iodine concentration effect, 459
Burst temperature, Zircaloy-4 cladding tube
versus burst pressure, 468 versus burst strain, 469 versus length change, 470
Burst test, 436 multi-rod, 473-475 transient, 551-553
CANDU-PHW pressure tubes, 189-202
behavior, 193-198
SUBJECT INDEX 809
cold-worked deuterium concentration, 195-
197 oxidation, 193, 195
critical oxide thickness, 196-197, 204-205
delayed hydride cracking, 227-229 deuterium concentration, cold-
worked Zircaloy-2 and Zr-2.5Nb pressure tubes, 195-197
in-reactor service life, 205 long-term kinetics, 198, 200-202 operating conditions for tubes re
moved from reactors, 194 oxidation pattern, inside surface
of cold-worked Zr-2.5Nb pressure tube, 198-199
Zircaloy-2 behavior, 190-191 Zr-2.5Nb, versus Zircaloy-2, 191-
193 see also specific alloys
CEA, 39
Cefilac, 39
Cesium/cadmium, stress corrosion cracking, 717, 725
Chemical inhomogeneity populations, 748-774
aqueous corrosion resistance, 762, 766, 768-770
carbon, 774 chemical nature, 760-761, 767 cladding cross sections, 757-758,
763-765 cladding ID surfaces, 752-757
diffuse appearance, 752-755 sharp inhomogeneities, 754,
756-757 electron microprobe analysis, 753,
755 energy-dispersive X-ray analysis,
748, 751-752, 756, 758, 773 fraction of inhomogeneities that
contain iron, 767 iodine SCC threshold stress, 768 materials, 750-751
occurrence of individual elements, 767
occurrence of specific combinations of elements, 767
procedures, 751-752 size
and SCC resistance, 761-762, 768
distribution, 758-760, 766 surface roughness data, 751
Chlorination, 136 Clad ballooning, heat transfer effect,
472, 474-476 Cladding oxidation, 504-538
i8-phase, 506 experimental design and conduct,
505 fuel rods heated in argon and oxy
gen as function of time, 506, 514-515
growth-rate equations, 506, 517 isothermal experiments, 506-517 metallic layer transformation as
function of time, 506, 516 microstructure, transient-heated
fuel-rod segments, 509, 518-520, 522-523
modeling results, 517, 521, 526, 528-536
isothermal experiments, 521, 526, 529-530
temperature transient experiments, 530-536
oxygen concentration distribution, interaction layers, 531-532, 534, 536
reaction-layer interfaces, movement as function of square root of time, 521, 529-530, 533, 535
reaction-zone thickness as function of
heat-up rate, cool-down rate, and maximum temperature, 509, 524-525
maximum temperature, 509, 526-527
810 ZIRCONIUM IN THE NUCLEAR INDUSTRY: SEVENTH SYMPOSIUM
Cladding oxidation (cont.) reaction-zone thickness as func
tion of {cont.) time, 506, 508, 510-513
sequence of external Zircaloy/oxy-gen and internal UOj/Zirca-loy interaction layers, 507
transient temperature experiments, 509, 518-527
Cladding tube, 292, 321, 539 sequence of operations, 342
Cold drawing, 149 Cold reduction, anisotropy effect,
653-662 procedure, 653-655 reduction parameter effects, 655-
657 tool design effect, 657-681
Cold-rolled Zircaloy-4 sheet, 555-575
anisotropy effects, 557-558 apparent activation energy evolu
tion, 567-568 cold-rolling and measurement
temperature effects, 558-561 composition, 556 evolution of solid solution during
Stages I and II, 565 influence of elements in solid solu
tion, 558 internal-friction experiments, 557,
562, 564 low temperature evolution, 562-
566 materials, 556 recovery, 566-571 recrystallization, 571-573 thermal treatments, 557 see also Thermoelectric power
measurements Cold rolling, 663 Cold working, 49, 431, 539, 653
effect on Zircaloy-4 thin strips, 666-669
irradiation growth effect, 60-63 Compressive properties, recrystal-
lized Zircaloy-4, 599-601
Constant opening angle, 593 Contractile strain ratio, 653-654,
662 Conversion yield, 136 Cookie-cutter electrode, 582 Coolability, deformed rod bundles,
480, 482, 484 Coolant flow direction, effect on flow
blockage, 474-478 Cooling, 451 Corrosion, 168, 206, 243, 292 Corrosion, 341
behavior of furnace /3-annealed tubing, 170-173
breakaway, 246-247 CANDU-PHW pressure tubes,
189 crud-induced localized, 257 effective parameter, versus Sn con
tent, 380, 382 first generation of laser-treated
Zircaloy tubing, 177 ID versus OD, 447 intermetallic precipitates, 315,
317-318 long term, cold-worked Zircaloy-2
and Zr-2.5Nb pressure tubes, 198, 200
microstructure relationship, 360-362
nodular accelerated, 207 rate as function of reciprocal tem
perature, 218 water chemistry effect, 190-191,
193 water-side, 417 Zircaloy-4 versus Zircaloy-2, 176,
178 Zr-2.5Nb, 189 see also Autoclave test; specific
types of corrosion Crack
critical length, 580 critical stress intensity factor, 580 elastic-plastic analysis, 592 growth rate, fatigue precracked
tubes, 710-711
SUBJECT INDEX 811
morphologies, irradiated Zircaloy cladding, 780, 782, 784-785
Cracking prevention, 224 surface, 612 velocity dependence on stress in
tensity factor, 224-225 see also Delayed hydride cracking
Crack initiation at chemical inhomogeneities, 749 during stress corrosion cracking,
717-733 active path mechanism, 717,
720, 725 annealing times, 720, 722 CH3I effectiveness in cracking-
resistant Zircaloy, 724, 729 incipient crack, 721, 731 intergranular cracking, 733 iodine reaction with silicone
rubber O-rings, 724-725 preheating effect on apparent
incubation time, 720, 724 procedure, 719 Rutherford backscattering spec
tra, 720, 722 small ductile tears, 730 transgranular features, 724,
728-729 typical initiation sites, 720, 724,
726-727 vacuum annealing effect on tex
ture after pickling, 720, 723 intergranular, 715
Crack propagation, 579, 700 expanding mandrel tests, 782,
784-785 incubation period, 715 internal gas-pressurization tests,
782 resistance to, 156-157
Crack resistance, CH3I effectiveness, 724, 729
Creep, 120, 168, 431, 597 cavitation, 629 compliance, 128 damage, 614, 629-630
diffusion-controlled, 7 isothermal/isobaric curves, Zirca-
loy-4, 461 recrystallized Zircaloy-4, 604
Creep elongation versus normalized annealing time,
444 versus yield strength, 440
Creep-fatigue cumulative damage, 606, 608-614
creep-then-fatigue sequence, 606, 608-610
fatigue-then-creep sequence, 606, 610-612
fatigue with hold time, 613-614 interaction, 597, 610
Creep loci crystallite orientation distribution
function, 123-125 CW-SR Zircaloy-4, 129-130 polycrystalline aggregate, 125,
128-129 ratios of hoop-to-axial strain-
rates, 131 recrystallized Zircaloy-4, 129-130,
132-133 shift from prism slip to basal slip,
132, 135 stress state, 129 total creep-rate, 128 Zircaloy, 120-135
Creep rupture test, 539, 551-553 deformation to failure, 704 under nominal stress, 608 Zircaloy-4 tube capsules, 464
Critical resolved shear stresses, 636 prism and pyramidal, temperature
dependence, 636, 639 Crystallite orientation, 120
distribution function, 123-125 Crystallographic texture, 23, 49, 51,
101, 120, 431, 653, 700 cold-rolled strips, 664-665 hydrostatically extruded and
drawn rods, 157-158, 165 intergranular crack initiation, 715 irradiation growth, 52-57, 93
812 ZIRCONIUM IN THE NUCLEAR INDUSTRY: SEVENTH SYMPOSIUM
Crystallographic texture (cont.) lower-bound predictions, 131 mechanical properties and, 666-
667 nodular corrosion, 389 recrystallized strips, 665-666 upper-bound predictions, 133 Zircaloy-4, 432, 434-435 Zr-2.5Nb pressure tubes, 88-89 see also Zircaloy-4 thin strips
Crystal plastic modeling. See Creep loci
c-Type Burger's vectors, 66-67, 70 Cubic Zr02 precipitates
dark-field stereopair images, 796 TEM microstructures, 787, 790-
791, 793 Cumulative damage, 597, 604, 606-
614 Cyclic behavior. See Zircaloy-4, cy
clic behavior Cyclic creep, 617 CYGRO program, 6
D
Damage rate, 5 Deformation
failure morphology and, 744-745 models, 632 Zircaloy. See Zircaloy, deforma
tion and fracture Degussa, 40 Delayed hydride cracking, 224-240
alloying effects, 231-232 crack initiation, 232-235
flaw depth requirements, 237 requirements, 236
crack propagation, 233-234, 236-237
crack velocity dependence on stress intensity
factor, 224-225 versus temperature, 233-236
examples, 225-229
flaws, 230, 237-238 hydrogen concentration, 230, 235,
237, 239 mechanism, 229 microstructure, 231-232 parameters of propagation, 237 prevention, 234-238 tensile stress, 230, 237-238 time dependency, 229-230
Density hydrostatically extruded and
drawn rods, 156-157, 163 Zirconium alloy strip, 116
Deuterium concentration in cold-worked Zir-
caloy-2 and Zr-2.5Nb pressure tubes, 195-197
pickup, garter springs, 204 Deutriding, 189 Dimple size, irradiation effect, 745-
746 Dislocation, 617
density, 49 Zr-2.5Nb pressure tubes, 89
loops, radiation-produced, 11 networks
cold-worked material, 545, 550 fully recrystallized material,
544, 549-550 structure
fatigued failed specimen, 624-625
irradiation growth, 94 substructure, 86, 629
formation and characteristics, 159, 166
Zr-2.5Nb pressure tubes, 89 Dislocation-climb-controlled creep,
7 Dissipative work, 123 Distribution function, 120 Dobes-Milicka's equation, 604-605 Dresden-2, 208-210 Ductile-brittle transition, 579
zirconium alloy pressure tubes, 594
SUBJECT INDEX 813
Ductility irradiated ZircaIoy-2 cladding, 737 loss, slow tensile tests, 710, 712 low temperature, hydrogen up
take, 463 Zircaloy-2, 590, 593 Zr-2.5Nb, 588-592
E
Economics, 35 Eighteen-grain model, 636, 638 Elastic-plastic fracture mechanics,
580 Elastic-plastic transition, 631, 652 Elastic strain, 602 Electrical resistivity
effect of recovery and recrystalliza-tion, 324
intermetallic precipitates, 313-314, 319
Electron microprobe analysis, chemical inhomogeneity populations, 753, 755
Electron microscopy, 341 Electro-refining cell
internally heated, 138-139 laboratory-scale, 137-138
Embrittlement, 451, 585 loss-of-coolant accident, 460-466 by synergistic effects, 797
Energy-dispersive X-ray analysis, 748, 751-752, 756, 758, 773
Enhancement factor, 217 Euler angles, 123-124 EXCEL
calandria tube, delayed hydride cracking, 227, 230-231
irradiation growth, 77, 79 Expanding mandrel tests, 675, 680-
682, 684-689 brittle-fracture site, 790-791, 793-
795 crack propagation, 782, 784-785 fracture surface morphologies,
783, 788-789
irradiated Zircaloy cladding, 778-779
method, 681-682 procedure, 684-685 purity, 688-689 results, 685-689 spent-fuel cladding results, 781 test matrix, 686 thickness, 689 tubing and foils used, 685 zirconium-barrier cladding, 680-
682, 684-689, 697 Extension creep curves, Zircaloy-4
cyclic behavior, 619, 622
Fabricated products, 35 Fabrication, 23 Failure elongation
temperature dependence, 738 unirradiated Zircaloy-2 cladding,
736 Failure morphology, 734
deformation and, 744-745 strain rate effect, 744
Fatigue continuous, 610 cumulative damage, 604, 606-609 curves, 603 damage, 614 with hold time, 613-614 low-cycle, 617 properties, 597
low cycle, recrystallized Zircaloy-4, 601-603
resistance, hold-time in tension effect, 614
Fatigue crack, 581 growth, 629
Fatigue-creep interaction, 610, 612 FEBA test, 482-484 Federal Republic of Germany, activi
ties during 1950-1960, 40
814 ZIRCONIUM IN THE NUCLEAR INDUSTRY: SEVENTH SYMPOSIUM
/-factors calculated versus experimental,
661 during reduction, 658
Fick equations, 528 Flaws, 224
delayed hydride cracking, 230, 237-238
FLIC, 18 Flow stress, 588, 590
J-resistance curve, 593 initial slope, 590, 593
tension and compression, 601 Fracture
analysis, hydrostatically extruded zirconium and Zircaloys, 153-154, 161
criterion, 580, 595 Zircaloy. See Zircaloy, deforma
tion and fracture Fracture surface, 585
fatigue precracked tube, 710-711 morphologies
brittle behavior, 776, 782-783, 786
expanding mandrel tests, 783, 788-789
internal gas-pressurization tests, 782, 786
Zircaloy-2, 782, 786 SEM, 746 Zircaloy-2, 587
Fracture toughness, 579, 584-585, 595-596
ductile behavior data, 591 factors controlling, 592-593 hydrostatically extruded and
drawn rods, 155 hydrostatically extruded zirco
nium and Zircaloys, 152-153, 155-160
maximum load versus temperature, 586
SEM of stretched zone, 161 Framatome, 41 France, activities during 1950-1960,
37-40
FR-2 tests, 460, 477, 481 Fuel cladding, 417 Fuel rod, 539
Garter springs, deuterium pickup, 204
Grain boundaries, 700, 715, 770 anisotropy factor, 53 parameters, irradiation growth ef
fects, 52-57 Grain shape
irradiation growth, 93-94 Zr-2.5Nb pressure tubes, 89
Grain size, 51, 291 cooling rate estimation, 317 irradiation growi:h, effect, 57-60 versus normalized annealing time,
443 subgrain, 554 yield strength and, 32-33, 439 Zircaloys, 293-294
Grid cell description, 103-104 irradiation-induced relaxation,
102-105 schematic, 102
Grid materials irradiation growth, 109-118 mechanical properties, 109-118
Grid spring materials, irradiation-induced relaxation, 105-109
Growth anisotropy factor, 53
H
Hafnium, 35 separation process, 39-40, 42
Hardening monotonous and cyclic curves, 601 static properties and, 611
Hardness hydrostatically extruded rod, 154,
161 intermetallic precipitates, 310,312
SUBJECT INDEX 815
Heat flux, nodular oxidation effects, 207-214, 216-217
Heat treatment, 321, 364, 367, 387, 417
Heraeus, 40 High-a-phase region, 539 High-pressure steam test, 368-372,
419-420 accumulation of temperature ef
fect after /3-quenching, 426-428
annealing after final cold-working, 425-
426 upper a-range after ;8-quench-
ing, 425 temperature effect before
quenching, 423-425 quenching rate effect, 424, 426 Zircaloy-4, 368-369
High temperature, 504, 539, 617 Hill's model, 632 History, 34-45
Belgium, 41 Campagnie Europeenee Ugine
Sandvik, 43-44 CEA, 39 Cefilac, 39 civil use, 36-37 Degussa, 40 Federal Republic of Germany, 40 France, 39-40 Heraeus, 40 Italy, 40-41 Jarrie, 42-43 Metallgesellschaft, 40 Military use, 36 Norway, 41 Pechiney, 39-40, 43 1950-1960 period, 37-41 1961-1970 period, 41-42 1971-1984 period, 43-45 prior to 1950, 35-36 Societe des Acieries d'Ugine, 37-
38, 42-43 Societe Industrielle du Zirconium,
41-42
Sweden, 41 Trefileries et Laminoirs du Havre,
39 United Kingdom, 36-37 Vallourec, 39
Hookes' law, 634 Hoop creep strain, 180-181 Hoop stress
distributions, 679 local, flaw effect, 680, 683 Zircaloy spent-fuel cladding, 782
Hydriding, 189 Hydride
cracking, unalloyed zirconium after burnup,699
stress orientation, 29-30 Hydriding, zirconium alloy pressure
tubes, 581-582 Hydriding-dehydriding, 136 Hydrogen, 489
concentration, 224 delayed hydride cracking, 230,
235, 237, 239 time to failure effect, 233, 235
effect on oxidation kinetics, 500 pickup
furnace /3-annealed Zircaloy-4, 173
long-term, Zircaloy-2 and Zr-2.5Nb pressure tubes, 200-201
steam dilution, 492-493 steam test effect, 271-274 uptake, 190-191
cold-worked Zircaloy-2 and Zr-2.5Nb, after extended exposure in reactor, 200-201
low temperature ductilbility, 463
Zircaloy, 502 Zircaloy-2 pressure tubes, 202
Hydrostatic extrusion, influence on properties, 149-167
deformation work and strength parameter of stress and strain field, 160
density, 156-157, 163
816 ZIRCONIUM IN THE NUCLEAR INDUSTRY: SEVENTH SYMPOSIUM
Hydrostatic extrusion {cont.) density (cont.)
change versus reduction of cross-sectional area, 163
dislocation substructure, 159, 166 evolution characteristics of tex
ture, 157-158, 165 experimental procedure, 150 fracture analysis, 153-154, 161 fracture characteristics, tensile
tests, 151-152, 155 fracture toughness, 152-153, 155-
160 generation of twins, 158 hardening, 154, 161 homogeneity of texture, 154, 156,
162 load versus displacement, 158-159 materials and preparation, 150 microvoid content, 147, 164 properties and microstructure
after annealing, 151, 153-154 after cold working, 150-152
resistance to crack propagation versus crack propagation, 156-157
tensile strength and ductility versus reduction of cross-sectional area, 151
Impurities, 364 In-reactor corrosion, 247 Intergranular crack initiation, crys-
tallographic texture, 715 Intermetallic particles, 341
billet-quenching, 346, 350, 352-353
chemistry, 349 clusters, 327, 329, 345 crystal structure, 349 density and distribution, 374, 376-
377 hollow |3-quenched Zircaloy-2,
351, 354-355
lattice parameter, 349 mean size, 349 morphology, size, and distribu
tion, 357-358 Zircaloy-2, distribution, 395-396,
398 Intermetallic phases, types, 333 Intermetallic precipitates, 307-320
activation energy and rate constant, 317
corrosion behavior, 315, 317-318 electrical resistivity, 313-314, 319 estimation of cooling rates during
i8-a transition from grain size, 317
experimental procedure, 308 hardness measurements, 310, 312 kinetics of nucleation and growth,
315-316 microstructure, 308-310 nodular corrosion, role, 395-408 nodule coverage, 317-318 stereologic characteristics, 318 thermal activation energies, 316 Zircaloy-2, 388 Zircaloy-4, 388
Internal-friction experiments, cold-rolled Zircaloy-4 sheets, 557
Internal gas-pressurization tests crack propagation, 782 irradiated Zircaloy cladding, 777 spent-fuel cladding results, 780
Intrinsic strength of the alloy, 17 Iodine-induced stress corrosion,
700-716 basal pole
intensity distribution, 704 orientation effect, 713
chemical inhomogeneity populations, 748, 770-771
deformation to failure, 704 mechanism, 714
procedure and materials, 701-703 slow tensile tests, 703, 710, 712 susceptibility, 712-714 threshold stress, 768 time to failure, 705-709
SUBJECT INDEX 817
see also Crack initiation, during stress corrosion cracking
Iodine zirconium high temperature growth, 77, 79 volume changes during irradia
tion, 78-80 Irradiated Zircaloy cladding, 775-
801 chemical analysis, 779 crack morphologies, 780, 782,
784-785 expanding mandrel test, 778-779,
781 internal gas-pressurization tests,
777, 780 irradiation-induced segregation as
function of temperature, 797-798
post-test examination, 779 pseudo-stereopair, 793 SEM fractographs, 782-783, 786,
788-789 specimen geometry and prepara
tion, 777 spent-fuel cladding, 777
Irradiation, 579 dimple size effect, 745-746 flux, nodular oxidation effect,
214-215 induced relaxation
grid cells, 102-105 grid spring materials, 105-109
nodular corrosion, effect, 408, 410 recrystallized Zircaloy-4, 54-55 zirconium alloy pressure tubes,
582-583 Zirconium alloy strip, 102 see also Zircaloy-2 cladding, irra
diated recrystallized Irradiation creep, 5, 7, 54
additive thermal and irradiation components, 11
Irradiation growth, 5, 49-82, 101 alloying additions and impurities,
73-78 anisotropy factor, 99 annealed
Zircaloy, 64 Zr-2.5Nb, 75-78
cold work effect, 60-63 crystallographic texture, 52-57, 93 dislocation structure, 94 displacement damage rates, 52 effect of low levels of cold-work
and stress-relieving heat treatments, 56-57
effect of oxygen on high temperature irradiation growth, 75
EXCEL, 77, 79 experimental procedure, 50-52 fractional recovery as a function of
cold work, 81 grain boundary
anisotropy factor, 53 parameter effects, 52-57
grain shape, 93-94 grain size effect, 57-60 grid materials, 109-118 growth anisotropy factor, 53 growth strain of Zr-0.1%Sn and
Zr-1.5%Sn alloys, 74, 76 microstructural changes to growth
breakaway, 66-70 microstructural effects, 86-99
crystallographic texture, 88-89 dislocation density, 89 dislocation substructure, 89 experimental procedure, 87-88 grain shape, 89 growth characteristics, 90-93 growth rate, 99 microstructure observed by
transmission electron microscopy, 96
prism pole/-parameters, 88 ratios of axial to transverse
growth strain, 99 stage 1 behavior, 97 stage 2 behavior, 97-98 stage 3 behavior, 98 substructures, 89-90
neutron flux intensity and high fluences effects, 61-66, 82
polycrystalline materials, 52
818 ZIRCONIUM IN THE NUCLEAR INDUSTRY: SEVENTH SYMPOSIUM
Irradiation growth {cont.) recrystallized Zircaloy-2, 53-55 recrystallized Zircaloy-4 sheet, 64-
65,67 single crystals, 51 strain as function of fast neutron
fluence, 93-96 temperature dependence of break
away growth, 64-65 test temperature and temperature
cycling effects, 70, 72-73 thermal stability, 79-81 volume changes, 78-80 Zircaloy-4, 113, 116-118 Zircaloy-2, grain size effect, 57-59 Zirconium alloy strip, 113
Isochronous annealing, microstruc-tural evolution stages, 563
Isothermal oxidation, 538 Italy, activities during 1950-1960,
40-41
Jarrie, 42-43 JMA law, 567 Jog-dragging model, 12 Johnson-Mehl-Avrami kinetic
model, 315 Johnson-Mehl-Avrami equation, 567 J-resistance curve, 579-580, 583
versus flow stress, 593 irradiation effect, 588 Zircaloy-2 containing radial hy
drides, 589, 592 Zr-2.5Nb, 588-589
K
Kula-Lopata technique, 121
Laser beam beta heat treatment, Zir-caloy, 168-186
corrosion behavior of furnace 0-annealed tubing, 170-173
hoop creep strain, 180-181 inner surface temperature, 184 irregular (3-phase penetration
caused by short temperature transient, 174, 176
main components, 173 microstructure, 174-176 partial-wall )3 treatment, 173, 182 partial-wall penetration, 185 properties of final-sized laser-
treated tubing, 176-180 residual stresses, 184 stress-rupture data, 179 tensile properties, 178-179
Legendre theorem, 125 Life fraction, 597
versus stress amplitude, 2 Light water reactor, 451, 504 Linear elastic fracture mechanics,
580 Load cyclic tests, 618-622, 626 Load follow, 597 Loci, 120; see also Creep loci Loss-of-coolant accident (LOCA),
451-485, 489 coolability of deformed rod bun
dles, 480, 482, 484 cooling, 451 core cooling acceptance criteria,
452 ECCS criteria, 466 embrittlement, 460-466 FR-2 in-pile tests, 460 materials, 690 metallographic cross section
nonbarrier Zircaloy, 693 Zr-barrier tube, 692
oxidation, 453-460 kinetics, 453
plastic deformation. See Plastic deformation
procedure, 689-691 results, 691 simulation multi-rod burst tests,
473-475 simulation ref lood tests in blocked
bundles, 483
SUBJECT INDEX 819
temperature as function of time, 690
zirconium-barrier cladding, 689-691, 697
see also Zircaloy-4 Low-cycle fatigue, 617
M
Manson-Coffin's law, 603 Martensitic structures, 284, 287 Material condition, 539 Mechanical properties, 5, 23, 101,
631, 663 after annealing, 151, 153 after cold working, 150-151 evolution during recovery and re-
crystallization, 567-569 grid materials, 109-118 initial, bent beam materials, 107 texture effect, 666-667 Zircaloy-4, 432, 436, 439 zirconium alloy strip, 111-113
Mechanistic modeling. See Zircaloy,
deformation and fracture Melting, 284 Metallgesellschaft, 40 Metallography, Zircaloy-4, 496-499 Metallurgical bond, 675
tenacity, 676 zirconium-barrier cladding, 676-
678 zirconium-Zircaloy interface, 676-
677 Microhardness, irradiated Zircaloy-4
strips, 113 Microstructure, 49, 149, 284-291,
307, 321, 341, 364, 387, 489 after phase transformation, 287 as-laser-treated tubes, 174-176 |3 heat treatment, temperature ef
fect, 288-289 i8-quenching, 371, 373 billet quenching, 437 cooling rate effect, 291 corrosion relationship, 360-362 delayed hydride cracking, 231-232
evolution stages, 563 high impurities content material,
288 high temperatures, 400 impurity effect, 287 intermetallic precipitates, 308-310 irradiation effects, 408, 410 low impurity content material, 288 material-bearing stringers, 288-
289 nodular corrosion, 369, 371, 373-
377 role of volatile impurities during
vacuum melting in stringer formation, 286
transient-heated fuel-rod segments, 509, 518-520, 522-523
Zircaloy-4, 432, 434, 436 deformed cold-worded cladding
tube, 545, 547 deformed fully recrystallized
cladding tube, 544, 546 Zircaloy, produced by recrystalli-
zation annealing, 343-347 Microvoid content
versus displacement from fracture, 164
hydrostatically extruded and drawn rods, 157, 164
Miner's law, 614 Modeling, 504 Molten-salt electro-refining process,
137-140 bath choice, 140 bench-scale demonstrated unit,
138-140 studies on laboratory cell, 137-138 see also Zircaloy scrap refining
N
Necking formation process, localized deformation band, 745
Neutron diffraction, 631 Neutron flux, intensity effect on irra
diation grovsrth, 61-66
820 ZIRCONIUM IN THE NUCLEAR INDUSTRY: SEVENTH SYMPOSIUM
Neutron irradiation, 5-7, 49 Nodular corrosion, 207, 307, 364-
429, 431 alloying elements impact, 379-384 alpha-recrystallized Zircaloy, 388 archive sample investigation, 421-
423 autoclave tests, 367 burnup effect, 420 concentration of solute elements of
grain matrices, 403, 409-410 critical particle diameter, 336 crystallographic texture, 389 data separation to identify mate
rial and reactor influences, 420-421
determination, 418-419 electrochemical model, 388-389 experimental procedures, 389-390 high pressure steam tests, 368-372 impurity elements impact, 384-
385 influence of fabrication sequence,
441 initiation and growth, 361 in-reactor/ex-reactor comparison,
390-393 irradiation effect, 408, 410 materials, 419 mechanism, 329 mechanistic effect of solute ele
ments, 400-401 microscopic analysis, 367-368 microstructural examinations, 418 microstructure, 369, 371, 373-377 models for solute distribution and
nodular oxide nucleation and growth, 410-413
normalized, 421-423. versus normalized annealing time,
445 out-of-pile simulation, 419 processing, 365-366 resistance, 321-337
intermetallic particle clusters, 327
materials, 322 SEM microstructure, 324-328 specimen preparation for SEM
and STEM, 322 specimens for metallography,
322 STEM microstructure, 325,
327, 330-332,334-335 types of intermetallic phases,
333 role of intermetallic precipitate
and solute distribution, 395-408
surface preparation effect, 283 susceptibility, 318
frequency of chemically inho-mogeneous sites, 769
thermochemical variable impact, 374, 378-379
versus volumetric mean size of precipitates, 424
weight gain versus distance from the surface
for, 438, 440 parameter X effect, 380, 383 sponge zirconium strip, as func
tion of annealing time, 401, 403
from static autoclave tests versus parameter X, 380-381
white sheet, 416 Zircaloy, 341 Zircaloy-4, 431, 434, 436-438 see also Autoclave test; Steam test;
specific Zircaloys Nodular oxidation, 206-223
average maximum coverage, 281 BWR spacer effect, 212-213 heat flux, 207-214, 216-217 incremental rate, 217 irradiation flux effect, 214-215 model, 219-220 nodular growth rate, 219-220 O2 concentration, 214-215, 217,
220-221 quantitative description, 215-220
SUBJECT INDEX 821
temperature effect, 215, 218-219 UO2, 208-210 Zircaloy, BWR spacer effect, 212-
213 Zircaloy-2, 208, 211-212
Nodular oxide granular, 413 nucleation and growth, 390-393
models, 410-413 sites, 393-394 steps leading to, 411-412
Zircaloy-4, 403, 409 Nodule coverage, 317-318 Nodulea, 168, 341 Norton creep equation, 539 Norton's equation, 604-605 Nuclear fuel cladding, 5 Nucleation, 307
O
Orientation basal pole effect, 165, 713 distribution functions, 125-127
using three pole figures, 135 preferred, 23, 25-26
Oxidation, 451, 489 computer codes for modeling,
457-458 hydrogen dissolved in oxide layers,
502 isothermal, 538
kinetics, 493-496 Zircaloy-4, 491-492
Zircaloy-4, 628 see also Loss-of-coolant accident,
oxidation; Nodular oxidation; Zircaloy-4, oxidation
Oxygen, 504 concentration
distribution in interaction layers, 531-532, 534, 536
nodular corrosion, weight gain, 384-385
nodular oxidation effect, 214-215, 217, 220-221
steam test effect, 270-272
Parallel plate structure, 284-285, 291
Pechiney, 39-40, 43 PECLOX model, 504-505, 517, 521,
528, 530, 532-533 theoretical basis, 528
Pellet-cladding interaction, 33, 675, 679, 717-718, 749, 775
Percentage uptake, 189 Perforated fuel rod, zirconium-bar
rier cladding, 691, 694-696 Phase, 168 Phase transformation, 284, 364
cooling rate effect, 291 stringers and microstructure after,
287 Phase transition, cooling rate estima
tion from grain size, 317 Physical properties, 149 Plasma melting, 136 Plastic deformation, 451, 466, 468-
480, 539-554, 606 a-phase, 470-471 application to nonstationary tem
perature conditions, 547-549 coolant flow direction on flow
blockage, 474-478 heat transfer effect on clad bal
looning, 472, 474-476 high a-phase region, 540 in-pile and out-of-pile behavior,
477, 480-482 multi-rod behavior, 471-473 partly recrystallized material,
550-551 procedure, 540-541 single-rod behavior, 466, 468-473 strain rate dependency
initial yield strength, 542-543 true stress, 541-542
under azimuthal temperature difference and cooling, 470-472
822 ZIRCONIUM IN THE NUCLEAR INDUSTRY: SEVENTH SYMPOSIUM
Plastic deformation (cont.) see also Burst temperature; Struc
ture parameter Plastic strain, 603, 634
radial, 654 Plate, 23 Pole figures, 23, 25-26
basal cold-rolled Zircaloy sheet, 665 intensity distribution, 704 orientation effect, 713 resolved fraction, 53 rod-textured Zircaloy-2, 636-
637 Zircaloy-4, 434-435
hydrostatically extruded and drawn rods, 154, 156, 162
inverse, 26 macro, 32-33 micro, 32-33 orientation density versus reduc
tion of cross-sectional area, 165
Zircaloy-4, 114-115, 121-122 Polycrystal equations, textured zirco
nium alloys, 635 Polycrystalline aggregate, creep
model, 125, 128-129 Polycrystalline deformation, 631-
632 Polycrystalline materials, irradiation
growth, 52 Polycrystalline zirconium, effects of
temperature on growth, 72-74
Power-cooling mismatch tests, 460 Power-law constitutive relationship,
128 Precipitates, 321, 387, 775
morphology, 307 nucleation and growth, 307
Pre-creep, 606 Pre-fatigue, 612 Preferred orientation, 23, 25-26 Pressure
autoclave test, 247 steam test, 263, 265, 267-268
Pressure tubes, 189, 579 Pressurized water reactor, 5, 307,
387, 451, 539 Prism pole/-parameters, 88 Proton migration theory, 329 Pseudo-stereopair, 793
Q-ratio, 120 Quenching, 364, 431
parameters, 367 rate effect, 424, 426
Q-value, 653
Radiation effects, 387 Radiation hardening, Zircaloy, 18 Reaction kinetics, 489, 504 REBEKA multi-rod burst tests, 475 Recovery, 555
cold-rolled Zircaloy-4 sheets, 566-571
kinetics carbon content effect, 571 cold-rolling effects, 568-570
mechanisms, 555 relative TEP evolution, 566 TEP applications, 559, 562
Recrystallization, 49, 120, 431, 555 cold-rolled Zircaloy-4 sheets, 571-
573 kinetics, 572-574
carbon content effect, 572-573 derived from TEP and mechani
cal properties measurements, 572, 574
recrystallized volume fraction, 571 relative TEP evolution, 566 TEP applications, 559, 562
Recrystallized Zircaloy-4, 597-616 creep behavior, 604 creep loci, 129-130, 132-133 creep-strained specimens, tension
and compression stress changes, 609
SUBJECT INDEX 823
damage cumulation, 604, 606-614 irradiation growth, 64-65, 67 low cycle fatigue behavior, 601-
603 material and methods, 598-599 metallographic examination, 614-
615 tensile and compressive proper
ties, 599-601 Reduction in area, 653-654 Reduction parameter, anisotropy ef
fects, 655-657 Reduction processes, 39-40 Residual strain
comparison of calculated and experimental values, 646-647
evolution, 648 grains of different orientation, 646
Residual stress, 49, 631 evolution during tensile deforma
tion, 641, 643-647 as function of increment in flow
stress, 642-643 for grains of different orientations,
643-645 intergranular, 729 room temperature, 637, 640 textured zirconium alloys, 635
Robinson's law, 614 Rocking, 30 Rod bundles, deformed, coolability,
480, 482, 484 Rupture behavior, Zircaloy-4, 619-
620 Rutherford backscattering spectra,
crack initiation during stress corrosion cracking, 720, 722
SAF2D, 679 Second phase, 86, 364 Second-phase morphology, 94-95 Second-phase particles, 292-306,
374, 376 chemical composition, 298, 327,
332
Cr/Fe ratios, 301, 303 crystal structure, 300 diameters of Zr(Cr, Fe) and Zr(Ni,
Fe) particles, 301 fuel rod average oxide thickness as
function of mean diameter, 300, 303
as function of Zr content, 302 materials and experimental proce
dure, 293-294 mean particle diameter, 296, 299 morphology, 294-296 oxide thickness, 305 particle composition, 296, 299,
302 plate-shaped, 329 produced by recrystallization an
nealing, 343 rod average oxide thickness versus
the ra t ion , 301, 304 SEM micrographs, 324, 326, 328 size distributions, 294-295, 324,
327 statistical distribution, 438 STEM analysis, 292, 294, 305 STEM micrographs, 327, 332,
334-335 volume fraction of precipitates,
300 Zircaloy-4, 434, 436, 438
Selected-area diffraction patterns, 783, 786-787
SEM microstructure, Zircaloy-2, nodu
lar corrosion resistance, 324-328
specimen preparation, 322 Severe fuel damage, 504 Shear strain-rate, 128 Shear stress, 128 Sheet, 23 Short time creep test, Zircaloy-4,
436, 440 SIMS, 401 Single crystal yield surface, 631
textured zirconium alloys, 633-634
824 ZIRCONIUM IN THE NUCLEAR INDUSTRY: SEVENTH SYMPOSIUM
Single-grain equations, textured zirconium alloys, 634-635
Slip, 120 Slow tensile tests
ductility loss, 710, 712 iodine-induced stress corrosion,
703, 710, 712 Societe Industrielle du Zirconium,
41-42 Solute-dislocation interactions, 555 Solutes, 49, 387 Spacer-grid, 101
improved heat transfer around, 476
Spent-fuel cladding, 775 characterization, 776 expanding mandrel tests results,
781 experimental procedure, 777 internal gas-pressurization stress
rupture test results, 780 Spring relaxation, 101 304 stainless steel
chemical composition, 619 load cycling, 626 stress ratio-lifetime curves, 620,
623 Steam-dilution experiment, 497-
498, 500 Steam reaction, 489 Steam test, 257-283
applications, 276-278 autoclave loop, 259 autoclave startup procedure ef
fects, 266-271 comparison of in-reactor and two-
step ex-reactor corrosion, 275-276
experimental procedure, 258-260 GE two-step steam test, 273-276
develop, 273-275 reproducibility, 275-276 test parameter specifications,
275, 277 hydrogen effect, 271-274 loop flow rate effects, 265-266,
269
occurrence frequency distribution, 280
oxygen effect, 270-272 parameters used in hydrogen addi
tion experiments, 273 parametric studies, 260 temperature effects, 260-261 temperature range of autoclave,
282-283 test duration, 260, 263-266 test pressure effects, 263, 265,
267-268 weight gains of Zircaloy-2
as function of autoclave startup procedure, 270-271
as function of flow rate, 269 as function of oxygen content,
271-272 as function of system pressure,
267 as function of test duration,
260, 263-264 as function of test temperature,
260-261 non-hydrogenated and hydro-
genated inlet steam, 272-274 tested in etched or prefilmed
condition, 273, 275 two-step test procedure, 276,
279-280 Steam UO2, 504 Stefan equations, 528 STEM analysis, 292, 294, 305
microstructure, Zircaloy-2, nodular "^corrosion resistance, 325, 327, 330-332, 334-335
specimen preparation, 322 studies, 333
Strain anisotropy, bending of Zircaloy-4
cladding in the a-phase, 471 dependency on time temperature,
and initial stress, 548-549 elastic, 602 plastic. See Plastic strain thermal. See Thermal strain total, 603
SUBJECT INDEX 825
Strain aging, 555 Zircaloy-2, 627 zirconium oxide, 627
Strain cyclic tests, 618, 621, 623-624, 626-627
Strain hardening, 606 exponent, 734
effects of irradiation, test temperature and strain rate, 742-743
Strain rate, 5,9 correlation with initial material
condition, 543-547 failure morphology effect, 744 initial yield strength dependency,
542-543 intermediate region, 16 Norton creep equation, 543 sensitivity, 734 tensile strength effect, 738 true stress dependency, 541-542 Zircaloy-2 cladding, 743-744
Strain ratio contractile. See Contractile strain
ratio differential, 658 local, 662 tool curvature section, 659-660
Strength, 168 Stress, 5, 9, 224 Stress amplitude
at end of fatigue damaging sequence, 609, 611
versus life fraction, 2 Stress corrosion cracking
resistance and chemical inhomo-geneity size, 761-762, 768
see also Chemical inhomogeneity populations; Crack initiation, during stress corrosion cracking
Stress intensity factor, 583, 585 cracking velocity dependence on,
224-225 critical, 580
Stress localization, zirconium-barrier cladding, 679-681
Stress ratio-lifetime curves 304 stainless steel, 620, 623 Zircaloy-4, 619-620
Stress relaxation, 597 kinetics, 613
Stress-relief, 101 Stress reorientation, hydrides in Zir-
caloy cladding, 29-30 Stress response, Zircaloy-4, 621, 623 Stress rupture failure, 239 Stress-rupture tests, Zircaloy-4 tube
capsules, 461, 465 Stress-strain curves, 600
irradiated recrystallized Zircaloy-2 cladding, 746
textured zirconium alloys, 637, 640-642
Stress-strain hysteresis loop, 647-648 Stringer
after phase transformation, 287 button samples, 291 formation role of volatile impuri
ties during vacuum melting, 286
a-Zr{0), 496 Structure parameter, 539, 544-546,
548-549 comparison of creep rupture tests
and transient burst tests, 553 dependency on normalized initial
stress, 550, 552 versus normalized stress and ex
tended normalized annealing time, 551
Superlattice reflection, 783, 787
Taylor's model, 632 Tear modules, hydrostatically ex
truded and drawn rods, 155 Temperature, 49
autoclave test, 246-247 Tensile properties, 88, 734
Zircaloy-2, 178-179 Zircaloy-4, 178-179
irradiated strip, 111-112
826 ZIRCONIUM IN THE NUCLEAR INDUSTRY: SEVENTH SYMPOSIUM
Tensile strength, 431 versus reduction of cross-sectional
area, 151 strain rate effect, 738
Tensile stress delayed hydride cracking, 230,
237-238 recrystallized Zircaloy-4, 599-601
Tensile tests characteristics of fractures, 151-
152, 155 zirconium alloy pressure tubes,
584 Test reproducibility, 257 Textured zirconium alloys, 631-625
active slip systems, 635 arbitrary stress, 633 Bauschinger effect, 647-648 polycrystal equations, 635 residual stress, 635
evolution during tensile deformation, 641, 643-647
residual thermal strains, 636, 638 residual thermal stress, 636, 639 single crystal yield surface, 633-
634 single-grain equations, 634-635 stress-strain curves, 637, 640-642 stress-strain hysteresis loop, 647-
648 Taylor's model, 632 thermal stress, 636-639 twinning, 651 uniaxial deformation, 637, 640-
641 Texture. See Crystallographic tex
ture Thermal stability, 49
irradiation growth, 79-81 Thermal strain, 634
residual, 636, 638 Thermal stress, 631
residual, 636, 639 textured zirconium alloys, 636-
639 Thermoelectric power, 555 Thermoelectric power measurements
apparatus, 557 application to study of recovery
and recrystallization, 559, 562
cold-rolled Zircaloy-4 sheets, 556-557
comparison with hardness evolution, 562
relative, variation with orientation from rolling direction, 558
reversibility of evolutions due to agings at low temperature, 563
Thick oxide, 189, 191,216 Tool design, anisotropy effect, 657-
681 Transformation, 168 Transient burst tests, 539, 551-553 Tube reducing, 30 Tubing, 23, 168
fabrication, 30-31 Twinning, textured zirconium alloys,
651
U
Uniaxial deformation, textured zirconium alloys, 637, 640-641
Uniform corrosion, 431 versus normalized annealing time,
445 Zircaloy-4, 434, 438, 440, 442
United Kingdom, activities prior to 1950, 36-37
United Kingdom Atomic Energy Authority, 36
UO2 nodular oxidation, 208-210 steam, 504
UOz/Zry interaction, 505-506, 508 oxygen saturation, 506
Vacuum melting, stringer formation, 286
Vallourec, 39
SUBJECT INDEX 827
Volume change, 49 irradiation growth, 78-80
W
Water chemistry, effect on corrosion and hydriding, 190-191, 193
Weertman pile-up mechanism, 7 Work softening, 649
Yield strength, 539 fluence dependence, 741-742 versus grain size, 439 initial
strain rate dependency, 542-543 structure parameter depen
dency, 552 irradiated Zircaloy-2 cladding,
737, 741 versus normalized annealing time,
443 unirradiated Zircaloy-2 cladding,
736 Zircaloy-4, 436, 439
Young's modulus, 734 defined, 739-740 fluence dependence, 740 irradiated recrystallized Zircaloy-2
cladding, 736, 739-740 temperature dependence, 741
Zircaloy, 364, 387, 504, 653, 675, 717
alpha recrystallized, nodular corrosion resistance, 388
amorphous Zr(Fe, Cr)2 precipitates, 70-71
annealed, irradiation growth, 64 anisotropy. See Anisotropy, Zirca
loy aqueous corrosion, 769 basketweave structure, 284-285 chemical composition, 344
cold-worked, 7-8 concentration of major solute/im
purity elements, 390 corrosion
rate, as function of reciprocal temperature, 218
second-phase particles, 292-306 creep loci. See Creep loci deformation and fracture, 5-20
annealed and cold-worked, 9-10 atomic-diffusion coefficient, 16 climb of dislocations over fixed
obstacles, 15 experimental and theoretical
background, 6-13 general proposed model, 17-18 high-stress region, 14-15 in-pile properties, 14 in-pile relaxation rates, 9-10 in-pile tests, 8 intermediate-stress region, 15-
17 intrinsic strength of the alloy, 17 jog-dragging model, 12 low-stress region, 13-14 mechanical deformation model,
18-19 model development, 13-18 Piercy's analysis, 11-12 radiation-enhanced diffusion,
16 radiation hardening, 18 radiation-produced dislocation
loops, 11 strain rate, 9 stress, 9 uniaxial, fixed-stress, in-pile
and unirradiated creep tests, 10-11
first-generation laser-treated, corrosion data, 177
gaseous stringers, 286 grain matrices of alpha recrystal
lized, 410-411 grain size, 293-294
and yield strength, 32-33 hydrogen uptake, 502
828 ZIRCONIUM IN THE NUCLEAR INDUSTRY: SEVENTH SYMPOSIUM
Zircaloy {cont.) irradiation creep, 7 laser /3-treated, corrosion data,
181 macro-grain, 32-33 metallographic determination of
interaction layer thickness, 506, 508
microstructure, immediately after laser treatment, 175
neutron irradiation, 6-7 nodular corrosion, 341 nodular oxidation. See Nodular
oxidation oxide weight gain, 294 parallel plate structure, 284-285 pellet cladding interaction, 33 relative concentrations of sinks, 7 scrap refining, 136-145
electro-deposit, 141-144 flowsheets for recycling on non-
remeltable scrap, 145 optimum conditions for electro-
refining, 139 particle size analysis, 142 purity, 141-142 space-time yield, 140-141 specific energy consumption,
140-141 see also Molten-salt electro-re
fining process transus beta/beta + silicide, 289 uniaxial creep tests, 8 uniform oxide growth rates, 204 see also Laser beam beta heat
treatment, Zircaloy; Steam test
Zircaloy-2, 23, 579 activation energy and rate con
stant, 317 autoclave test. See Autoclave test behavior, 190-191 beta quenching, 28 billet-quenched, 346, 349-350 brittle behavior, 586-587 chemical composition, 293 cold-worked, 9
irradiated in ATR and DIDO reactors, 62-63
microstructural parameters, 61-62
pressure tubes, 202 containing radial hydrides, /-resis
tance curve, 589, 592 corrosion versus weight gain,
HPST, 422-423 creep rates, 9 crystal structures, 300-301 deformation, 635
work and strength parameter of stress and strain field, 160
degree of ellipticity, 28 degree of matrix supersaturation,
303 dislocation microstructures, 66,
68-69 ductility, 590, 593 effect of low levels of cold-work
and stress-relieving heat treatments on irradiation growth, 56-57
electrical resistivity change during isothermal annealing, 313-314
failure probability, 235 fracture surfaces, 587 grain size effect on irradiation
growth, 57-59 hardness change during isother
mal annealing, 312 high alpha temperature annealing,
336 high temperature growth, 77, 79 hollow /3-quenched, intermetallic
particles, 351, 354-355 hydrogen uptake, 190-191 in-reactor service life, 205 intermetallic particle
clusters, 345 distribution, 395-396, 398
intermetallic precipitates, 388 irradiation growth, cold-worked
and cold-worked/stress-relieved, 61-62
SUBJECT INDEX 829
laser beam beta heat treatment, 169
microdiffraction, 346 microhardness distribution, 161 microstructure
after rapid |8-quenching, 308-311
annealed rods, 154 jS-quenched, 359-360 rods hydrostatically extruded
and drawn, 152 nodular corrosion. See Nodular
corrosion / nodular oxidation, 208, 211-212 nodular oxide, 3 9 0 - 3 ^
growth as function of exposure time, 390, 392
normalized particle size and autoclave data, 360
occurrence frequency distribution, 280
polycrystalline, basal pole concentration, 27
post-transition corrosion data, laser /3-treated tubing, 178
pressure tubes cold-worked, 193, 195-197 stages in corrosion kinetics, 190 water chemistry effect on in-re-
actor corrosion, 192-193 versus Zr-2.5Nb, 191-193
produced by recrystallization annealing, 343-344
recrystallized irradiation growth, 53-55 temperature dependence of
breakaway growi:h, 64-65 relative mass intensity of solute el
ements, 407 relative solute concentrations in
precipitate-free grain matrices, 408
rod textured, eighteen-grain
model, 636, 638 second-phase volume fractions,
329 single crystals, 31
solute concentrations in grain matrix, 411
spheroidal-type precipitates, 400 steady-state irradiation growth as
function of dislocation density, 61, 63
steam test, 259 strain aging, 627 TEM, 399 temperature cycling and irradia
tion growth, 73 tensile properties, 178-179 test claddings, manufacturing
characteristics, 293 twinning, 651 weight gains
annealing temperature and, 396-397
etched or prefilmed condition, 273, 275
final annealing temperature effect, 324
as function of autoclave startup procedure, 270-271
as function of flow rate, 269 as function of oxygen content,
271-272 as function of system pressure,
267 as function of test duration,
260, 263-264 as function of test temperature,
260-261 non-hydrogenated and hydro-
genated inlet steam, 272-274 precipitate number density, 396 steam autoclave test, 357 temperature effect, 323 using two-step test procedure,
276, 279-280 yielding creep, 11 zirconium-lined, 400-404
Zircaloy-4, 101, 431-447, 539 activation energy and rate con
stant, 317 anisotropy, 114-115 autoclave test. See Autoclave test
830 ZIRCONIUM IN THE NUCLEAR INDUSTRY: SEVENTH SYMPOSIUM
Zircalay-4 (cont.) basal pole figure, 434-435 i3-quenched, 113 j3 treatment, 432 billet quenching, 349, 351-353,
434, 437 burst strain
versus azimuthal temperature difference, 477, 481
versus burst temperature, 469, 482
cladding tubes versus azimuthal temperature difference, 470, 473
initial iodine concentration effect, 459
burst temperature versus burst pressure, 468
changes in infrared emissivity, 503 chemical composition, 619 cladding deformation and flow
blockage under reversed flow, 477-478 under unidirectional flow, 477,
479 cladding tube
deformation, influence of heat transfer, 474, 476
length change versus burst temperature, 470
cold-rolling effect on absolute TEP, 560
creep loci, 129-130, 132-133 critical oxide thickness, 204-205 crystallographic texture, 121-122,
432, 434-435 cyclic behavior, 617-630
extension creep curves, 619, 622 load cycling, 619-622, 626 load-extension behavior, 619,
621 materials, 618-619 microstructural observations,
624-626 procedure, 618 strain cycling, 621, 623-624,
626, 627
deformation sensitivity to temperature, 469 wire texture, 157
density, 157 ductility of tubes, 431 Euler plot representing ODF, 126 experimental procedure, 432, 434 fabrication and history, 366 fabrication sequences, 432 /-factors, 436 furnace /S-annealed tubing, 170-
173 corrosion data, 172 hydrogen pickup data, 173 micrographs, 171
grain size, final size recrystallized tubes, 436, 438
high pressure steam tests, 368-369 high temperature steam oxidation
comparison of mass increase during LOCA-similar transients with those of isothermal exposure, 458
mass increase after different hypothetical accident transients, 457
mass increase versus time of exposure, 455
parabolic rate constant versus reaction temperature, 456
hoop creep strain data, 180-181 ingot size and composition, 365 intermetallic particles, 347-348 intermetallic precipitates, 388 irradiated, tensile properties, 111-
112 irradiated microhardness, 113 irradiation growth, 113, 116-118
as function of cold work and fluence, 60
isothermal/isobaric capsule tests, 461, 463, 465
isothermal/isobaric creep curves, 461
isothermal oxidation, 491-492 kinetics, 493-496
laser |3-treated, 169
SUBJECT INDEX 831
stress rupture data, 179 mechanical properties, 432, 436,
439 melting, 496 microstructure, 110, 432, 434, 436
after quenching from /S-phase, 427
iS-quenched, 359-360 deformed cold-worked cladding
tube, 545, 547 deformed fully recrystallized
cladding tube, 544, 546 microvoid content, 157 nodular corrosion, 431, 434, 436-
438 susceptibility, 318
nodular oxide, 390-391, 403, 409 normalized particle size and auto
clave data, 361 oxidation, 489-503, 628
apparatus, 490 experimental procedure, 489-
493 hydrogen effect on kinetics, 500 metallography, 496-499 parabolic-rate constants, oxide
layer growth, 494-495 steam-dilution experiment,
497-498, 500 steam oxidation in hydrogen,
492-493 temperature gradients, 492
oxidized tube capsules, crack pattern, 461-462
pole figures, 114-115, 121-122 inverse, 162
post-transition corrosion data, laser i3-treated tubing, 178
pressure tubes delayed hydride cracking, 227,
229 hydrogen pickup, 200-201 long-term corrosion, cold-
worked, 198, 200 out-reactor corrosion, 191-192
processing schedules, 433 produced by recrystallization an
nealing, 344 recrystallized
Euler plot representing ODF, 127
irradiation growth, 54-55, 64-65,67
recrystallized. See Recrystallized Zircaloy-4
rupture behavior, 619-620 second-phase particles, 434, 436,
438 shell stage, 434, 436 steam oxidation, 453 strain rate dependency
initial yield strength, 542-543 true stress, 541-542
stress ratio-lifetime curves, 619-620
stress response, 621, 623 tensile properties, 178-179 tube wall after double-sided steam
oxidation, 454 uniform corrosion, 434, 438, 440,
442 UO2 and oxygen reaction-zone
thicknesses, 506, 510-513 weight gains
annealing temperature and, 396-397
precipitate number density, 396 refreshed high pressure steam,
374, 378-379 steam autoclave test, 357
see also Cold-rolled Zircaloy-4 sheets
Zircaloy-4 bar, chemical analysis, 598
Zircaloy cladding hydride stress orientation, 29-30 inhomogeneity distributions, 749-
750 see also Iodine-induced stress cor
rosion; Loss-of-coolant accident
Zircaloy-2 cladding irradiated recrystallized, 734-742
832 ZIRCONIUM IN THE NUCLEAR INDUSTRY: SEVENTH SYMPOSIUM
Zircaloy-2 cladding (cont.) irradiated recrystallized (cont.)
effects of irradiation, test temperature, and strain rate on strain hardening exponent, 742-743
failure elongation temperature dependence, 738
irradiation conditions, 735 irradiation effect on dimple size,
745-746 materials, 735 procedure, 735-736 specimen appearances after
testing, 739 strain rate effect, 743-744
failure morphology, 744 tensile strengths, 738
strength and ductility, irradiated specimens, 737
strength and failure elongation, unirradiated specimens, 736
stress-strain curve, 737, 740-743, 746
Young's modulus, 736, 739-740 Zircaloy-4 cladding tubes, 700
material condition of laboratory-annealed, 540-541
Zircaloy-4 fuel rod cladding, load in double-ended cold leg break LOCA, 452
Zircaloy sheet, cold-rolled, basal pole figure, 665
Zircaloy-4 sheet annealed textures, 666 see also Cold-rolled Zircaloy sheet
Zircaloy-4 thin strips, 663-672 annealing temperature effect, 667,
670-671 cold working influence, 666-669 material, 663-664 textures
cold-rolled strips, 664-665 evolution, 672 mechanical properties and,
666-667 recrystallized strips, 665-666
Zircaloy-4 tube capsule isothermal/isobaric creep-rupture
tests, 461, 464 stress-rupture tests, 461, 465
Zircaloy-2 tubing, expanding mandrel test, 686, 688
Zirconium absolute TEP, evolution with tem
perature, 559 concentration depth profile, 406 concentration of major solute/im
purity elements, 390 white sheet oxide, 416
Zirconium alloy, 49, 243, 364, 489 textured. See Textured zirconium
alloys see also Delayed hydride cracking
Zirconium alloy pressure tubes, 579-596
brittle behavior, 584-588 ductile-brittle transition, 594 factors controlling fracture tough
ness, 592-593 flow stress, 588, 590 fracture criterion, 580 hydriding, 581-582 irradiation, 582-583 leak-before-break, 579 load deflection curves, ductile and
brittle specimens, 584 procedures, 583-584 tensile tests, 584 test specimens, 581
Zirconium alloy strip, 101-119 density, 116 initial mechanical properties of
bent beam materials, 107 irradiation conditions, 102 irradiation growth, 113 mechanical properties, 111-113 unrelaxed stress ratio
irradiated bent beam materials, 108
irradiated cells, 104-105 see also specific alloys, 113
Zirconium-barrier cladding, 675-699
SUBJECT INDEX 833
bond effect, 679-683 expanding mandrel tests, 680-
682, 684-689, 697 hoop stress distributions, 679
local, flaw effect, 680, 683 irradiated, 677-678 loss-of-coolant accident, 689-691,
697 metallurgical bond, 676-678 metallurgically bonded Zr-barrier
tubing and nonbarrier Zirca-loy tubing, 684
nonbonded Zr-foil liners in Zirca-loy tubing, 684
perforated fuel rod, 691, 694-696 power ramp, 679, 682 stress localization, 679-681
Zirconium carbide, 284, 290 Zirconium chloride, 284 Zirconium cubes, dimensional
changes, 80, 82 Zirconium hydride, 579, 581-582
bulk, TEM microstructures, 793 local concentration, 770
Zirconium oxide, 362, 412-413, 453, 491-492
growth on Zircaloy-4, 493-494 parabolic-rate constants, 494-495 precipitates, TEM microstruc
tures, 783, 786-787, 790-791 stability and nature under nonirra-
diation conditions, 801 strain aging, 627 time-temperature dependence of
embrittlement, 463 Zirconium phosphide, 284, 290 Zirconium silicide, 284, 289-290 Zirconium sponge, 35, 37-38, 41-42
commercial purity, 681 irradiation growth, 75 low oxygen, 699
corrosion, 401-402 photomicrographs, 401, 404-
405
microstructure, 393-394 production in France, 38 weight gain as function of anneal
ing time, 401, 403 Zirconium-Zircaloy interface, metal
lurgical bond, 676-677 Zr-8.6A1 alloys, irradiation growth,
78,80 Zr-2.5Nb, 579
as-extended, microstructure, 89-90
delayed hydride cracking, 227, 229, 232-233
dislocations, 89 ductility, 588-592 failure probability, 232-234 fuel element, delayed hydride
cracking, 226-227 high temperature growth, 77, 79 in-reactor service life, 205 irradiation growth, 75-78 /-resistance curve, 588-589 versus Zircaloy-2, 191-193 see also Irradiation growth, micro-
structural effects Zr-2.5Nb pressure tube
cold-worked, 202 deuterium concentration, 195-
197 long-term corrosion, 198, 200 oxidation, 193, 195
current specifications, 88 delayed hydride cracking, 225,
227-228 flow diagram of production routes,
87 hydrogen pickup, 200-201 kinetics, 192 metallurgical characteristics, 89 out-reactor corrosion, 191-192 oxidation pattern on inside sur
face, 198-199 substructure, 90-92