Journal of Nuclear Materials 1992: Vol 191-194 Table of Contents

9 Pages·1992·3.5 MB·English

Contents
PART A Section 2. Tritium Breeding Materials
2.1. Fabrication and properties
Measurements of the effective thermal conductivity of
a bed of Li,SiO, pebbles of 0.35—0.6 mm diameter
Section 1. Plenary and Invited Papers
and of a mixed bed of Li,SiO, and aluminum
pebbles, M. Dalle Donne, A. Goraieb and G. Sordon 149
Prospects and strategy for the development of fusion Implications of beryllium: steam interactions in fusion
SI TE IE. 5.6 :6 in ahhe 68 wae 844549 reactors, G.R. Smolik, B.J. Merrill and R.S. Wallace
Global energy scenarios and the potential role of fu- Compatibility test of Be with Li,O (1) — diffusion
sion energy in the 21st century, R.S. Pease couple test, N. Sakamoto, H. Kawamura, E. Ishit-
Properties and performance of tritium breeding ceram- suka and Y. Ichihashi 158
ics, N. Roux, C. Johnson and K. Noda .......... Compatibility of stainless steels and lithium based ce-
BEATRIX-II: A multinational solid breeder materials ramics with beryllium, 7. Flament, D. Herpin, L.
experiment, G.W. Hollenberg, H. Watanabe, J.J. of POTeTre eS ee e eS Pe
Hastings and S.E. Berk Compatibility behavior of beryllium with LiAlIO, and
jee Oe. £8 eee 2 2 ee re, 2 ie 8
Structural materials for high-heat flux applications, Li,ZrO, ceramics, with 316 L and 1.4914 steels in
ffm Sse errerr rrere ee SIBELIUS, N. Roux, J.J. Abassin, M. Briec, D. Cruz,
The application of austenitic stainless steels in ad- T. Flament and I. Schuster ........0000c0000. 168
vanced fusion systems: . current limitations and Mass spectrometric study on the formation of LiOD (g)
future prospects, A. Kohyama, M.L. Grossbeck and by reaction of Li,SiO, (cr) with D,O (g) or D, (g),
G. Piatti R.-D. Penzhorn, H.R. thle, §. Huber, P. Schuster and
LTLererewee oar ee 2 4 fc | ee ee me oe we me ee we eT Oe |
Search for low-erosion carbon materials, J. Roth, C. reneres eee ae ee ee ee
Garcia-Rosales, R. Behrisch and W. Eckstein Mechanical and microstructural properties of tritium
“ee @e
Deformation and fracture in irradiated austenitic stain- permeable PdAg alloy after helium implantation,
less steels, G.R. Odette and G.E. Lucas R. Lindau, A. Moslang and R.-D. Penzhorn 178
iwnwen @.e @
Radiation-induced changes in the physical properties Surface characterization of hot-pressed beryllium with
of ceramic materials, S.J. Zinkle and E.R. Hodgson X-ray photoelectron spectroscopy, E. Ishitsuka, H.
Radiation-induced microstructural change in ceramic Kawamura, K. Ashida, M. Matsuyama, K. Watanabe,
materials, C. Kinoshita H. Ando and Y. Futamura
sie hE ACO SSR EOS ee SEAR DO. 6
Composite materials for fusion applications, R.H. Jones,
C.H. Henager, Jr. and G.W. Hollenberg .........
2.2. Irradiation and tritium transport and release
Vanadium alloys for structural applications in fusion
systems: a review of vanadium alloy mechanical and
physical properties, B.A. Loomis and D.L. Smith . . 84 Preliminary interpretation of the LIBRETTO-2 experi-
Evaluation of reduced-activation options for fusion ma- mental results in terms of tritium permeation bar-
terials development, D.R. Harries, G.J. Butterworth, rier efficiency, E. Proust, P. Leroy and H.W. Fra-
A. Hishinuma and F.W. Wiffen 0.0..0 0.00. 00 0s 92 nenberg 186
St £62 hs b8 4-4 64 09.0.5 £62 Sd 6 62 42 OOO OR
The status and prospects of high-energy neutron test Transport of tritium in liquid lithium, H. Moriyama, K.
facilities for fusion materials development, T. I CE 0 6-0 aes MAO Os OW ode oh 190
Kondo, D.G. Doran, K. Ehrlich and F.W. Wiffen 100 Neutron damage in beryllium, D.S. Gelles and H.L.
Molecular dynamics studies of defect production and Heinisch 194
a6 8-6 oe 84-6 6 42H 6 BD 66. 2.4 6 Oe oe ee a eS
clustering in energetic displacement cascades in Management options for used lithium ceramic breeder
copper, 7. Diaz de la Rubia and W.J. Phythian .... materials, J.H. Miles and G.J. Butterworth ....... 199
Ferritic/ martensitic steels: promises and problems, Effects of oxygen potential on tritium release from
R.L. Klueh, K. Ehrlich and F. Abe ............. Li,O, D. Yamaki, S. Tanaka and M. Yamawaki .. . 204
Influence of primary recoil energy spectrum on mi- Hydrogen transports through gas/liquid Li,;Pb,, in-
crostructural evolution, M. Kiritani terface and metal membrane contacting the alloy,
6S 2 4682 e 8-8 S
Compatibility of materials in fusion first wall and blan- S. Tanaka, M. Yamawaki, K. Yokoo, K. Kurita and
ket structures cooled by liquid metals, 7. Flament, R. Kiyose 209
P. Tortorelli, V. Coen and H.U. Borgstedt ........ In situ tritium recovery from Li,O irradiated in fast
Materials issues in the design of the ITER first wall, neutron flux — BEATRIX-II temperature change
blanket, and divertor, R.F. Mattas, D.L. Smith, C.H. specimen, O.D. Slagle, T. Kurasawa, R.A. Verrall
Wu, T. Kuroda and G. Shatalov 139 ee ES re re ee
Terra 2:9 2s 2-2 3 & 6
Contents
Hydrogen isotope permeability through austenitic steels Carbon-based materials thermal development testing
18Cr—10Ni-—Ti and 16Cr—11Ni-3Mo-Ti during re- and selection process for first wall and divertor
actor irradiation, B.G. Polosuhin, E.P. Baskakov, applications, D.A. Bowers and J.W. Sapp
E.M. Sulimov, A.P. Zyryanov, Yu.S. Shestakov, G.M. Resistance of carbon-based materials for the ITER
Kalinin, Yu.S. Strebkov and A.G. Dobrynskih divertor under different radiation fluxes, 7.A. Burt-
The behaviour of diffusion and permeation of tritium seva, O.K. Chugunov, E.F. Dovguchits, V.L. Ko-
through 316L stainless steel with coating of TiC and marov, I.V. Mazul, A.A. Mitrofansky, M.I. Persin,
Ti+N Ti C, C. Shan, A. Wu, Y. Li, Z. Zhao, Q. Yu.G. Prokofiev, V.A. Sokolov, E.I. Trofimchuk and
Chen, Q. Huang and S. Shi L.P. Zav’jalsky
LIPSIE device: Pb-17Li irradiation in water loop with Thermal wave characterization of plasma-facing mate-
on-line tritium measurements, G. Thevenot, F. rials by IR radiometry, B.K. Bein, J. Gibkes, J.H.
Lefevre, J. Estrade, M. Roche, T. Flament and A. Gu, R. Hiittner, J. Pelzl, D.L. Balageas and A.A.
Terlain Déom
Tritium release from lithium aluminate: can it be im- Microstructure and some properties of boron modified
proved?, J.P. Kopasz, C.A. Seils and C.E. Johnson graphite USB-15, V.N. Chernikov, V.Kh. Alimov,
Temperature programmed desorption from LiAlO, A.E. Gorodetsky, V.M. Sharapov, A.P. Zakharov
treated with H,, A.K. Fischer and E.I. Kurolenkin
Influence of grain-size and carbonate impurities on the Chemical interaction of hydrogen with graphite in re-
tritium release from lithium orthosilicate, H. Wede- gard of hydrogen recycling and chemical erosion of
meyer, H. Werle and E. Giinther fusion reactor first wall material, M. Yamawaki, K.
Irradiation behavior of LiAlO, and Li,ZrO, ceramics Yamaguchi, M. Satoh and S. Tanaka
in the ALICE 3 experiment, B. Rasneur, G. On the characterization of graphite, 7. Tanabe, K.
Thevenot and Y. Bouilloux Niwase, N. Tsukuda and E. Kuramoto
Radiation damage in pure and Al-doped Li,SiO,, K. Annealing experiment of ion-irradiated graphite by
Noda, Y. Ishii, T. Nakazawa, H. Matsui, N. Igawa, laser Raman spectroscopy, K. Niwase, T. Tanabe
D. Vollath, H. Ohno and H. Watanabe and I. Tanaka
Tritium transport in lithium ceramics porous media, Thermal shock of carbon based materials and coatings
S.W. Tam and V. Ambrose under high heat flux, J.P. Qian, X. Liu, P.Y. Li and
Recombination coefficients of deuterium on metal sur- Z. Guo
faces evaluated from ion-driven permeation, 7. Na- In situ EELS observation of diamond during hydrogen-
gasaki, R. Yamada and H. Ohno ion bombardment, K.N. Kushita, K. Hojou, S. Fu-
Thermal absorption and desorption of deuterium in runo and H. Otsu
beryllium and beryllium oxide, R.G. Macaulay-New- Radiation damage of graphite due to hydrogen-ion
combe, D.A. Thompson and W.W. Smeltzer bombardment at very low temperature, K.N.
In-situ luminescence measurement of lithium alumi- Kushita, K. Hojou and S. Furuno
nate under ion beam irradiation, Y. Asaoka, H. Initial damage in graphite under ion irradiation stud-
Moriyama, K. Iwasaki, K. Moritani and Y. Ito ied by real-time Raman measurement, M. Kitajima
and K. Nakamura
2.3. Liquid breeding materials
Thermal desorption spectroscopy of pyrolytic graphite
Tritium release behavior from molten lithium—lead cleavage faces after keV deuterium irradiation at
alloy by permeation through stainless steel type 330-1000 K, Y. Gotoh, T. Yamaki, K. Tokiguchi and
304, T. Terai, K. Uozumi and Y. Takahashi H. Shimizu
Thermodynamic and experimental evaluation of the Initial erosion experiments in the steady state high flux
sensitivity of Pb-17Li breeder blankets to atmo- plasma source MAP (materials and plasma), H.
spheric contamination, P. Hubberstey and T. Sample Bolt and S. Tanaka
Is Pb-17Li really the eutectic alloy? A redetermination Hydrogen solubility and diffusivity in neutron-irradia-
of the lead-rich section of the Pb—Li phase diagram ted graphite, H. Atsumi, M. Iseki and T. Shikama
(0.0 <x, (at%) < 22.1), P. Hubberstey, T. Sample Experimental and analytical studies on thermal erosion
and M.G. Barker of carbon-based materials with high thermal con-
Behavior of Po-210 in molten Pb-17Li, H. Feuerstein, ductivity, M. Akiba, M. Araki, S. Suzuki, H. Ise, K.
J. Oschinski and S. Horn Nakamura, K. Yokoyama, M. Dairaku and S. Tanaka
Diffusion and retention of helium in graphite and
Section 3. Plasma-Facing Components
silicon carbide, P. Jung
3.1. Graphite and carbon-carbon composites Thermal properties of carbon—boron-titanium com-
pounds as plasma facing materials, 7. Tanabe, T.
The effect of neutron irradiation on the structure and
Baba, A. Ono, M. Fujitsuka, T. Shikama and H.
properties of carbon-carbon composite materials, Shinno
T.D. Burchell, W.P. Eatherly, J.M. Robbins and J.P.
3.2. Non-graphitic materials
Strizak
Thermal erosion behaviour of carbon and boron- Response of solute and precipitation strengthened cop-
carbon materials during simulated plasma disrup- per alloys at high neutron exposure, F.A. Garner,
tions, H. Bolt, H. Madarame, T. Sukegawa and S. M.L. Hamilton, T. Shikama, D.J. Edwards and J.W.
Tanaka Newkirk
Contents
Potential collector surface materials for divertors, H.E. irradiation, G. Schumacher, N. Wanderka, R.P. Wahi
Prebble, C.B.A. Forty and G.J. Butterworth 39] and H. Wollenberger 478
‘6 € 2'4°% 0 £62 8 2 0 0 6 OO OR O'S
Void formation in neutron-irradiated Cu and Cu al- Some problems of brazing technology for the divertor
loys, K. Yamakawa, I. Mukouda and Y. Shimomura 396 plate manufacturing, Yu.G. Prokofiev, V.R. Bara-
Radiation-resistant properties of copper alloys in- bash, V.F. Khorunov, S.V. Maksimova, A.A. Ger-
tended for fusion reactor applications, /.V. Gorynin, vash, S.A. Fabritsiev and V.F. Vinokurov ........ 483
S.A. Fabritsiev, V.V. Rybin, V.A. Kasakov, A.S. Brazing of copper—alumina alloys, C.K. Lee, B.A. Chin,
Pokrouskii, V.R. Barabash and Y.G. Prokofiyev 401 S. Zinkle and R.C. Wilcox 488
Effects of neutron irradiation on structural stability Development of beryllium bonds for plasma-facing
and mechanical properties of copper alloys for components, E. Franconi, G.C. Ceccotti and L.
ITER divertor, E.V. Nesterova, V.V. Rybin, S.A. IE aii Vhs en le RTE Kaeo 493
Fabritsiev and V.R. Barabash 407 Analysis of sweeping heat loads on divertor plate mate-
Microstructural evolution and swelling of copper alloys rials, A. Hassanein 499
‘wie 4 @24 €@ DOO CBS DSO OS OBES
under ion irradiation, V.R. Barabash, A.A. Gervash, Thermal response of substrate structural materials dur-
A.N. Naberenkov, E.V. Nesterova, V.V. Rybin and ing a plasma disruption, A. Hassanein and D.L.
S.A. Fabritsiev 411 Smith 503
SCG OG 86 HO .6 6 9.4 4-85 6S. Ge S24 SE. 8 npn d-f 8): 4 2D B4S6 2. C.F SO 44 6/828 Se ad
Irradiation performance of oxide dispersion strength- Plasma deposited boronized carbon films, V.M. Shara-
ened copper alloys to 150 dpa at 415°C, DJ. Ed- pov, A.I. Kanaev, A.P. Zakharov and A.E. Gorodet-
wards, K.R. Anderson, F.A. Garner, M.L. Hamilton, BP es ca ROR SS ARE hie eek 508
J.F. Stubbins and A.S. Kumar ........0.00000055 416
Effects of neutron irradiation on properties of refrac-
Section 4. Ceramic and Composite Materials
tory metals, .V. Gorynin, V.A. Ignatov, V.V. Rybin,
S.A. Fabritsiev, V.A. Kazakov, V.P. Chakin, V.A.
4.1. Microstructure and properties
Tsykanov, V.R. Barabash and Y.G. Prokofyev 421
Effects of neutron irradiation on physical and mechani-
cal properties of Mo-—Re alloys, §.A. Fabritsiev, High-temperature mechanical and material design for
V.A. Gosudarenkova, V.A. Potapova, V.V. Rybin, SiC composites, N.M. Ghoniem 515
Eorteteatene <2 oe
L.S. Kosachev, V.P. Chakin, A.S. Pokrovsky and Potential for use of high-temperature superconductors
V.R. Barabash 426 in Comes SORCINTD, CAE. FE ok ket dsc cde sues 520
e464 & 6 6 6 2D SD oD £:-36e Oo SO O08 84 S88
Hydrogen embrittlement considerations in niobium- Fabrication and physical properties of AIF,—BeF,
base alloys for application in the ITER divertor, based fluoride glasses for IR transmission, H. Ohno,
D.T. Peterson, A.B. Hull and B.A. Loomis 430 N. Igawa, Y. Ishii, N. Umesaki and M. Tokita ..... 525
Deuterium interaction with impurities in tungsten stud- New potentials for high mechanical strength grades of
ied with TDS, H. Eleveld and A. van Veen 433 polycrystalline alumina for EC waves windows, A.
Hydrogen permeation and diffusion in molybdenun, T. Ibarra, R. Heidinger and J. Molla 530
$4e£2€6 64.486 09.6 63%
Tanabe, Y. Yamanishi and S. Imoto 439 An intercomparison of techniques for measuring di-
22 0 628 6 8 6 Oe
Hydrogen permeation study with atomic hydrogen electric permittivity and loss over a wide frequency
Sh oD dbs 'tie nds 460045 > 4c 0 Oo eR a 444 range, G.P. Pells, R. Heidinger, A. Ibarra-Sanchez,
Radiation damage induced by plasma exposures under H. Ohno and R.H. Goulding
een 2g 4 686442 Se 4
long duration tokamak discharge in TRIAM-1IM, Microstructure and mechanical properties of CVI car-
K. Tokunaga, T. Muroga, T. Fujiwara, K. Tawara, N. bon fiber/SiC composites, 7. Noda, H. Araki, F.
Yoshida, S. Itoh and the TRIAM Group 449 Abe and M. Okada 539
Heat load material studies: simulated tokamak disrup-
tions, J.M. Gahl, J.M. McDonald, A. Zakharov, S.
4.2. Effects of irradiation on physical and mechanical proper-
Tserevitinov, V. Barabash and M. Guseva 454
ties
Electron beam disruption simulation on coated materi-
als, G. Rigon and F. Brossa 460
oe 4 2 6/68 £60: 8 C4 Oe. 6.8
Study of radiation induced conductivity by ac-method
Enhanced resistance of plasma-sprayed TiC coatings to
in a fission reactor, 7. Shikama, M. Narui, Y. Endo,
thermal shocks, R.G. Saint-Jacques, F. Bordeaux, B.
Stansfield, G. Veilleux, W.W. Zuzak, A. Lakhsasi, C. Fi ST GN TE, TD no vc ccc casceuese 544
Radiation-induced conductivity in alumina from 100
eee ae G, GH oi 'xcb oo bein dé 6 eoS ke 465
Hz to 10 MHz during proton irradiation, E.H.
3.3. Fabrication and analysis of plasma-facing components Farnum, J.C. Kennedy, F.W. Clinard and H.M. Frost
Radiation enhanced electrical breakdown in fusion in-
Development of graphite /metals bondings for fusion sulators from de to 126 MHz, E.R. Hodgson
a4 ane
reactor applications, F. Brossa, E. Franconi and P. Reduction of the mechanical strength of Al,O,, AIN
Schiller 469 and SiC under neutron irradiation, W. Dienst
Stability of phosphorus intermetallic compounds dur- Radiation induced microstructure and mechanical
ing irradiation of nickel-based alloys used in braz- property evolution of SiC/C/SiC composite mate-
ings, L. Boulanger, P. Bellon, Y. Serruys, N.V. Doan rials, L.L. Snead, S.J. Zinkle and D. Steiner ...... 560
and G. Martin 473 Measurement of the effect of radiation damage to
Stability of phases in joints brazed with Ni-P (BNi6) ceramic composite interfacial strength, L.L. Snead,
and Ni—Cr—P (BNi7) alloys under 300 keV Ni* ion TA Se EE Ds ce hae e cd eee eeeen 566
XIV Contents
Electrotransport and radiation effects in alumina insu- Q.R. Huang, L.L. Peng, O. Mao, J.J. Du, Z. Lu and
lators during high temperature reactor applications, X.Z. Liu
R.H. Zee, WY. Wu and B.A. Chin Phase stability of reduced-activation Mn-stabilized
Radiation induced conductivity of ceramic insulators austenitic steels, J.J. Cole, D.S. Gelles and J.J. Hoyt
measured in a fission reactor, 7. Shikama, M. Narui, Microstructural and mechanical characterization of new
Y. Endo, T. Sagawa and H. Kayano low-activation Cr—Mn austenitic steels, G. Piatti, D.
Electrical conductivity changes in silicon carbide under Boerman and F.D.S. Marques
y-ray irradiation, S. Kasahara, Y. Katano, S. Shi- High temperature strength of simple and solute-mod-
manuki, K. Nakata and H. Ohno ified 10Cr—30Mn austenitic steels, F. Abe, T. Noda,
In-situ observation of damage evolution in SiC crystals H. Araki and S. Nakazawa
during He* and H3 dual-ion beam irradiation, K. Thermal fatigue behavior and dislocation substructures
Hojou, S. Furuno, K.N. Kushita, H. Otsu and K. Izui of 316-type austenitic stainless steels, A.F. Armas,
X-ray line broadening in neutron irradiated silicon I. Alvarez-Armas and C. Petersen
carbide, T. Iseki, T. Yano and H. Miyazaki The effect of temperature on the low cycle fatigue of
Development of irradiation small capsule for in-reactor type 316L stainless steel over the range 20-—200°C,
measurement of electrical properties of fusion reac- T.E. Chung, M.R. Kalantary, R.G. Faulkner and
tor materials, M. Narui, T. Shikama, Y. Endo, T. J.-L. Boutard
Sagawa and H. Kayano High temperature creep behaviour of 12Cr—-20Mn-—W
Effects of Cr,O, on electrical conductivity during y-ray austenitic stainless steel, L./. Ivanov, E.V. Dy-
irradiation in single crystalline Al,O,;, Y. Katano, omina, K. Mili¢ka and J. Cadec
K. Nakata, S. Kasahara and H. Ohno Influence of tungsten, carbon and nitrogen on tough-
Measurement of dielectric properties in ceramics un- ness and weldability of low activation austenitic
der ionizing and displacive irradiation conditions, high manganese stainless steels, Y. Hosoi, Y. Shi-
R.E. Stoller, R.H. Goulding and S.J. Zinkle moide, M. Abraham, M. Kutsuna and K. Miyahara
Linear stability analysis of helium-filled cavities in SiC, Thick-section weldments in 21-6-9 and 316LN stainless
H. Huang and N. Ghoniem steel for fusion energy applications, D.J. Alexander
Irradiation behavior of carbon—boron compounds and and G.M. Goodwin
silicon carbide composites developed as fusion re- Suppression of HAZ cracking during welding of he-
actor materials, 7. Shikama, M. Fujitsuka, H. Araki, lium-containing materials, C.A. Wang, H.T. Lin,
T. Noda, T. Tanabe and H. Shinno M.L. Grossbeck and B.A. Chin
Effect of neutron irradiation on fracture toughness of
metal matrix composites, $. Sato, K. Hamada and
5.1.2. Radiation effects on microstructure and properties
A. Kohyama
Temperature dependence of the dislocation mi-
4.3. Effect of irradiation on microstructure crostructure of PCA austenitic stainless steel irradi-
ated in ORR spectrally-tailored experiments, P.J.
Radiation-induced swelling of polycrystalline alumina Maziasz
over the temperature range 200-890 K, G.P. Pells Study of Fe—12Cr—20Mn-—W-C austenitic steels irradi-
and M.J. Murphy ated in the SM-2 reactor, V.K. Shamardin, T.M.
Lattice location and clustering of helium in ceramic Bulanova, V.S. Neustroyev, Z.E. Ostrovsky, V.M.
oxides, W.R. Allen and S.J. Zinkle Kosenkov, L.I. Ivanov and E.V. Diomina
Characteristics of the loop formation process in the Microstructural evolution of austenitic stainless steels
MgO-AI,O, system irradiated with fission neu- irradiated in spectrally tailored experiment in ORR
trons, K. Nakai, K.-i. Fukumoto and C. Kinoshita at 400°C, T. Sawai, P.J. Maziasz, H. Kanazawa and
Macroscopic length, lattice parameter and microstruc- A. Hishinuma
tural changes in neutron-irradiated aluminum ni- Effects of irradiation on the microstructure of IN-
tride due to annealing, 7. Yano, M. Tezuka, H. CONEL 600 alloy, J.-J. Kai and R.D. Lee
Miyazaki and T. Iseki Microstructural changes in welded joints of 316 SS by
Defect formation in ion-irradiated Al,O, and dual-ion irradiation, A. Kohyama, Y. Kohno, K.
MgAl,O,: effects . of grain boundaries and fusion Baba, Y. Katoh and A. Hishinuma
transmutation products, R. Yamada, S.J. Zinkle and Microstructural changes of 316L stainless steel under
G.P. Pells energetic alpha particle and proton irradiation at
Anisotropic dislocation loop nucleation in ion-irradia- 500°C, J. Yu, Y. Chen, Q. Yang, Y. Shi, Y. Yao, X. Li
ted MgAl,QO,, S.J. Zinkle and Y. Wang
Electron irradiation induced structure-phase transfor-
PART B
mation in low radioactivation chromium-—
manganese steel, L./. luanov, L.N. Bystrov, Yu.M.
Section 5. Structural Materials
Platov, V.M. Lazorenko, G.G. Bondarenko, O.M.
5.1. Austenitic steels Kasjanov and V.M. Ustinovshchikov
The analysis of microstructure of helium bubbles in
5.1.1. Microstructure and properties 316L SS induced by 3.02 MeV He ion irradiation,
Measurement of hydrogen solubility, diffusivity and K.Q. Chen, S.H. Yang, Z.G. Wang, J.G. Sun, J.M.
permeability in HR-1 stainless steel, B.Q. Deng, Quan, L.W. Li and Y.M. Sun
Contents
Microstructural evolution of titanium modified The weldability of low activation Cr—W steels, C.A.
austenitic stainless steel after FFTF irradiation, Y. Wang, R.L. Klueh and B.A. Chin 831
e¢ e¢ #2 49 2 9 8
Kohno, A. Kohyama and H. Kayano 742 Effects of temperature on the low cycle fatigue and
‘ee 4 4-a2° 839 2 4
Multiple ion implantation effects on hardness and fa- microstructures of HT-9 ferritic steel, H.J. Chang
tigue properties of Fe—13Cr—15Ni alloys, G.R. Rao, Ce NSE ra eee rer ees eet 836
E.H. Lee, L.A. Boatner, B.A. Chin and L.K. Mansur 748 Dislocation substructures developed in martensitic
Helium effects on the post-implantation creep proper- steels under thermal fatigue, /. Alvarez-Armas, A.F.
ties and the microstructure of AISI 316L welds and Armas and C. Petersen 841
parent material, Y. Dai and H. Schroeder 754
£4 » @ @ 2 6
Microscopic tritium behavior in ion-irradiated
austenitic steels, §. Yamamoto, Y. Ishida, N.
A Se ae ee re ee ee re 759 5.2.2. Radiation effects on microstructure and properties
Fast neutron irradiation hardening of austenitic stain- Tensile properties of neutron irradiated 9Cr-WVTa
less steel at 250°C, J.D. Elen and P. Fenici 766 steels, F. Abe, T. Noda, H. Araki, M. Narui and H.
Tensile properties of austenitic stainless steels and Kayano ‘Oo e2ie & ES e @ 6 2S OOD.S OS-8-8. S O.4- Se C4232 3-5RS 845
their weld joints after irradiation by the ORR-spec- Effect of neutron irradiation on the dynamic fracture
trally-tailoring experiment, S. Jitsukawa, P.J. Mazi- toughness behaviour of the 12% Cr steel MANET-I
asz, T. Ishiyama, L.T. Gibson and A. Hishinuma 771 investigated using subsize V-notch specimens, C.
Dependence of the tensile properties of 316 L parent Wassilew and K. Ehrlich 2 £68 2 @ 24 * 8H C4 4-H 08 850
material and welds on implanted hydrogen and/or Radiation embrittlement and recovery annealing regu-
helium, H. Schroeder and W. Liu ............. 776 larities of ITER blanket 9Cr steel, Yu./. Zvezdin,
Helium concentration dependence of embrittlement O.M. Vishkarev, G.A. Tulyakov, Yu.G. Magerya, V.A.
effects in DIN 1.4970, 13% cw austenitic stainless Smirnov, 1A. Shenkova, I.V. Altovski, A.A. Grigo-
steel at 873 K, H. Schroeder and Y. Dai 781 ryan, V.K. Shamardin and U.M. Pecherin ........ 855
a 2s Se SH 3
Mechanical properties and fracture behavior of a par- Irradiation-induced grain and lath boundary segrega-
ticle irradiated type 316 stainless steel at high tem- tion in ferritic—martensitic steels, R.G. Faulkner,
perature, K. Miyahara, A. Itoh, Y. Sakamoto, H. ak. Ee OS Beaks EE “eho kde ene awe 858
A Eree ee r ee a ee 786 The tensile and fatigue properties of DIN 1.4914
Stress—strain relations of irradiated stainless steels be- martensitic stainless steel after 590 MeV proton
low 673 K, S. Jitsukawa, M.L. Grossbeck and A. irradiation, P. Marmy and M. Victoria
66 CNS od od be awd eee eee as 790 Irradiation response of a reduced activation Fe-—8Cr-
Cyclic endurance and thermocyclic damage of 0.04C- 2W martensitic steel (F82H) after FFTF irradia-
16Cr—11Ni-3Mo-0.05Ti steel unirradiated and tion, Y. Kohno, D.S. Gelles, A.K ohyama, M. Tamura
neutron irradiated steel, VV. Rybin, V.F. Vi- ro A IE ere ee ee er ee ee 868
nokurov, N.B. Odintsov, L.A. Belyaeva and L.G. Microstructural change on electron irradiated oxide
PE 5.G eiss bb h SOO Oe eae ee 795 dispersion strengthened ferritic steels, H. Kinoshita,
The interaction of fatigue and creep in weldments of N. Akasaka, H. Takahashi, I. Shibahara and S.
AISI 316L austenitic steel after helium implanta- Onose SSCA PADD E SASHA EOS CB Ae CE OOS O14 2 OOO SG 874
tion, M. Paulus, H. Schroeder and J. Deutz 798 Effects of alloying elements on the post-irradiation
Determination of the creep compliance and creep- microstructure of 9%Cr-2%W _ low activation
swelling coupling coefficient for neutron irradiated martensitic steels, A. Kimura, M. Narui and H.
titanium-modified stainless steels at ~ 400°C, M.B. Kayano . es ) 6 56 '6 6 Oe © @ F' O16 OO 6.6 0.4.6 £8 4S 6 Oo OO 879
Toloczko, F.A. Garner and C.R. Eiholzer ........ 803 Irradiation induced changes in the grain boundary
Modeling of strengthening mechanisms in irradiated chemistry of high-manganese low activation
fusion reactor first wall alloys, M.L. Grossbeck, P.J. martensitic steels, A. Kimura, L.A. Charlot, D.S.
Maziasz and A.F. Rowcliffe 808 Gelles, D.R. Baer and R.H. Jones 885
eh DS sh 6&4 64'S S SB. 8 2 4-OO
Irradiation and thermal creep of a titanium-modified The microstructure of the 1.4914 MANET martensitic
austenitic stainless steel and its dependence on cold steel before and after irradiation with 590 MeV
work level, F.A. Garner, M.L. Hamilton, C.R. Ei- protons, D. Gavillet, P.M army and M. Victoria 890
holzer, M.B. Toloczko and A.S. Kumar 813 Heat treatment effects on toughness of 9Cr—-1MoVNb
The blistering of 316L stainless steel irradiated with and 12Cr—1MoVW steels irradiated at 365°C, R.L.
energetic alpha particles at 500°C, J. Yu, Y. Chen, 6. ig ido 0% :4.8 W ie Wel as 896
¥, aoe GD Fae Y. FOO GWE E, BF niccc eieces s 818 Effect of neutron irradiation on the strength of elec-
tron beam welded JFMS steel, K. Fujii, K. Ogawa
5.2. Ferritic steels
and S. Kaga 901
5.2.1. Microstructure and properties Tensile behavior and microstructure of the helium and
Accumulation of engineering data for practical use of hydrogen implanted 12% Cr-steel MANET, K.K.
reduced activation ferritic steel: 8%Cr-2%W- Bae, K. Ehrlich and A. Moslang 905
0.2% V-0.04%Ta-—Fe, N. Yamanouchi, M. Tamura, Helium implantation effects on low activation 9Cr
H. Hayakawa, A. Hishinuma and T. Kondo 822 martensitic steels, A. Hasegawa and H. Shiraishi 910
On size and geometry effects on the brittle fracture of Behavior in fatigue-relaxation of a creep resistant 12%
ferritic and tempered martensitic steels, G.R. Cr steel after helium implantation, R. Lindau and
Odette, B.L. Chao and G.E. Lucas 827 rl PP ee ee ee eee ee eee 915
XVi Contents
5.3. Vanadium alloys Effects of compositional modifications on the sensitiza-
tion behavior of Fe—Cr—Mn steels, G.L. Edgemon,
P.F. Tortorelli and G.E.C. Bell 997
5.3.1. Microstructure and properties Radiation effects on grain boundary chemistry relevant
Embrittlement of vanadium alloys doped with helium, to stress corrosion cracking of stainless steels, E.P.
H. Matsui, M. Tanaka, M. Yamamoto and M. Tada Simonen, R.H. Jones and §.M. Bruemmer
Vanadium alloys as structural materials for liquid Stress corrosion cracking and intergranular corrosion
lithium blanket of fusion reactors, V.A. Evtikhin, of neutron irradiated austenitic stainless steels, K.
LE. Lyublinski, V.Yu. Pankratov and L.P. Zavyalski Fukuya, S. Shima, H. Kayano and M. Narui
Effect of gamma irradiation on stress corrosion behav-
ior of austenitic stainless steel under ITER-relevant
5.3.2. Radiation effects on microstructure and properties
conditions, R.H. Jones and C.H. Henager, Jr.
Structural and phase changes and radiation damage in
Radiation-induced sensitization of a titanium-modified
low-activation vanadium-—titanium alloys on elec-
austenitic stainless steel irradiated in a spectral-
tron and neutron irradiation, L.J. Ivanov, V.V.
tailored experiment at 60—400°C, 7. Inazumi, G.E.C.
Ivanov, V.M. Lazorenko, Yu.M. Platov and V.1.
Bell, P.J. Maziasz and T. Kondo
Tovtin
Microstructural investigation of helium and lithium
5.5. Test techniques, data storage and fabrication methods
effects in V—Ti alloys irradiated in FFTF by means
of '°B-doping, H. Kawanishi, Y. Arai and S. Ishino
Neutron irradiation damage of helium-charged V-—Ti- Small specimen test techniques for the evaluation of
Cr-Si-type alloys, M. Satou, K. Abe and H. Matsui toughness degradation, M. Suzuki, M. Eto, Y.
Correlation of microstructure and tensile and swelling Nishiyama, K. Fukaya, M. Saito and T. Misawa 1023
behavior of neutron-irradiated vanadium alloys, Development of a tensile test system for irradiated
H.M. Chung and D.L. Smith specimens by robot operation, A. Okada, S. Igarashi
High swelling rates observed in neutron-irradiated and Y. Kakazu
V-Cr and V-Si binary alloys, F.A. Garner, D.S. R&D of an automated tensile machine for heavily
Gelles, H. Takahashi, S. Ohnuki, H. Kinoshita and neutron irradiated materials, A. Kohyama, S. Sato
B.A. Loomis and K. Hamada
Effect of solute addition on swelling of vanadium after An electric potential drop technique for characterizing
FFTF irradiation, H. Nakajima, S. Yoshida, Y. part-through surface cracks, M. Enmark, G. Lucas
Kohno and H. Matsui and G.R. Odette 1038
Low swelling behavior of V—Ti—Cr-—Si-type alloys, M. Information and computer-aided system for structural
Satou, K. Abe, H. Kayano and H. Takahashi materials, Ju.G. Nekrashevitch, Sh.U. Nizametdinou,
A.V. Polkovnikov, V.P. Rumjantzev, O.N. Surina,
G.M. Kalinin, A.V. Sidorenkov and Ju.S. Strebkov
5.4. Environmental effects System design of pilot data-free-way (Distributed
database for advanced nuclear materials), H. Naka-
jima, N. Yokoyama, S$. Nomura, F. Ueno, M. Fujita,
5.4.1. Liquid metals
Y. Kurihara and S. Iwata
The effects of hydrogen and Pb—17Li on the tensile
Helium generation rates in isotopically tailored Fe-
properties of 1.4914 martensitic steel, 7. Sample, V.
Cr-Ni alloys irradiated in FFTF/MOTA, L.R.
Coen, H. Kolbe and L. Orecchia
Greenwood, F.A. Garner and B.M. Oliver
Dissolution kinetics of steels exposed in lead-lithium
Alloy preparation for studying the effect of hydrogen
and lithium environments, P.F. Tortorelli
production during neutron irradiation using >*Fe
Behaviour of $S316, with and without aluminization, in
isotope, M. Suzuki, A. Hishinuma, N. Yamanouchi,
stagnant Pb—17Li, 1. Schreinlechner and P. Sattler
M. Tamura and A.F. Rowcliffe
Comparison of austenitic and martensitic steels be-
On-line weld position control for fusion reactor weld-
haviour in semi-stagnant Pb17Li, J. Sannier, T.
ing, S. Nagarajan, H.C. Wikle III and B.A. Chin .. .
Dufrenoy, T. Flament and A. Terlain
Selective surface preoxidation to inhibit the corrosion
5.6. Miscellaneous materials
of AISI type 316L stainless steel by liquid Pb—17Li,
T. Sample, V. Coen, H. Kolbe and L. Orecchia
Mass transfer of 316L steel in Pb17Li CLIPPER loop Permeation behavior of deuterium implanted into alu-
minium-—lithium alloys, 7. Hayashi, K. Okuno and
after 12000 hour running, A. Terlain, T. Flament,
T. Dufrenoy and J. Sannier
The solubility of metals in Pb—17Li liquid alloy, H.U. Restoration phenomena of Ti—-Ni shape memory alloys
in a neutron irradiation environment, 7. Hoshiya, S.
Borgstedt and H. Feuerstein
Shimakawa, Y. Ichihashi and M. Nishikawa 1070
Radiation resistance and parameters of activation of
5.4.2. Stress corrosion and aqueous corrosion aluminium—magnesium-scandium and alumin-
Corrosion behavior of stainless steels in aqueous salt ium—magnesium—vanadium alloys under neutron
blanket option solutions for ITER, D.J. Duquette, irradiation, L.J. Ivanov, V.V. Ivanov, V.M. La-
K.L. Wrisley, E. Coomer and D. Steiner zorenko, Yu.M. Platov, V.I. Tovtin and L.S. Toropova
Contents
Section 6. Radiation Effects on Microstructure tion, S. Kojima, T. Yoshiie, K. Hamada, K. Satori
and M. Kiritani 1155
—PRRE Ate ee eee a ee ee a a oe
6.1. Primary damage and collision cascades Detection of the role of free point defects from the
variation of defect structures near permanent sinks
Molecular dynamics and binary collision modeling of in neutron irradiated metals, 7. Yoshiie, S. Kojima,
the primary damage state of collision cascades, Y. Satoh, K. Hamada and M. Kiritani .......... 1160
H.L. Heinisch and B.N. Singh .......0.00.000585 1083 Modeling of microstructural evolution under cascade
The variation of the cascade localization induced bias damage, K. Kitajima $4689 €@ 26824 £20666 SOS OOS 1166
effect with material parameters and irradiation con- Void swelling in copper and copper alloys irradiated
ditions, 7. Yoshiie and M. Kiritani ............. 1088 with fission neutrons, B.N. Singh, A. Horsewell, D.S.
Analytical description of disordering during cascade Gelles and F.A. Garner be Sd Stee Oe OS. 6 OS. S 6. 6 RS 1172
evolution in ordered intermetallics, C. Abromeit Tensile property changes of metals irradiated to low
and H. Wollenberger 1092 doses with fission, fusion and spallation neutrons,
aa e as 4 6 oh 6°02 42.958 OSS Se
The impact of spectral effects in fast reactors on data H.L. Heinisch, M.L. Hamilton, W.F. Sommer and
analysis and development of fission—fusion correla- PR 56 dt aise ated deaitan aa 1177
tions, L.R. Greenwood, F.A. Garner and H.L. Effect of additional minor elements on microstructural
Heinisch 1096 evolution of neutron irradiated Fe—Cr—Mn alloys,
'¢ ese Os 6 8 68 2S 6 EOE OAD OS DESO OOD
Binary collision calculation of subcascade structure and H. Takahashi, S. Ohnuki and H. Kinoshita ...... 1183
its correspondence to observed subcascade defects A study of sink strength of dislocations through kinet-
in 14 MeV neutron irradiated copper, Y. Satoh, T. ics of loop formation under electron irradiation, K.
Yoshiie and M. Kiritani See vnee 606 0 8 64 £4 © 88-8 1101 Nakai, C. Kinoshita and Y. Muroo 2 4 tia Gwe 6 6.e £8 1189
Nonlinear effect of atomic displacements and created Growth rate of dislocation loop in Fe-—Ni-Cr alloy
defects in irradiation cascades, N.V. Doan, F. Rossi under Kr~* ion and electron irradiation, 7. Kimoto,
and L. Boulanger 1106 C.W. Allen and L.E. Rehn eee 0 Oe. @ 64 8 26 2 6 Oo O'S 1194
Molecular dynamics study of the displacement thresh- Microstructures of neutron-irradiated Fe—12Cr—X Mn
old surfaces and the stability of Frenkel pairs in (X = 15-30) ternary alloys, K. Miyahara, F.A. Gar-
B-SiC, A. El-Azab and N.M. Ghoniem ae om oe ee 1110 ner and Y. Hosoi he0% £8 2 H' ROOD 4 46 OOO 8'O OF O'S eG 1198
Microstructural changes in Fe—10Cr—2Mo steel by
neutron or charged particle irradiation, Y. Katoh, Y.
6.2. Defect clusters from cascades
Kohno, A. Kohyama and H. Kayano 1204
se + 64.2 44°62 @
Formation of interstitial loops on transmutation prod-
Low dose fission neutron irradiation on P- and Ti-mod-
ucts in aluminum, K. Ono, H. Ogawa, S. Furuno, T.
ified austenitic alloys with improved temperature
Kino, N. Kamigaki, K. Hojou, Shibatani, Y.
control, N. Yoshida, Q. Xu, H. Watanabe, T. Muroga
Kageyama, K. Mizuno and K. Ito 1209
CO aS Seyee eee ee e ee 1114
Evolution of structural damage in aluminum alloys
Accumulation processes of cascade damage under
irradiated with helium ions, N. Kamigaki, S. Fu-
heavy ion irradiation, Y. Kanzaki, N. Sekimura and
runo, K. Hojou, K. Ono, E. Hashimoto, K. Izui and
S. Ishino 1119
.£O2 2 Ow Se OE O82 2.9 6.88 OO 60 OH 2S 6.8 Oe Oe T. Kino 1214
Thermodynamical evaluation of cascade damage evolu- oe &¢ 2.4.9 & 6.80 tc SO Oe CSO SS. Oo. 22S S988
In-situ observation of structural changes in aluminum
tion by molecular dynamics calculation, K. Mor-
during He* and H3 dual-ion beam irradiation, S.
ishita, N. Sekimura, T. Toyonaga and S. Ishino ... .
Furuno, K. Hojou, K. Izui, N. Kamigaki, K. Ono and
Self-ion irradiation of fcc metals to elucidate primary
T. Kino 1219
recoil energy dependence of defect structure devel- ‘nee oS? € OOO O42 OS ON OSA OHS DS 4 ORO
opment during neutron irradiation, M. Kiritani, H.
Kato, M. Hoshino, H. Matsui and N. Matsunami . 1128 6.4. Cavity formation and swelling
Effect of helium on defect cluster formation in modi-
fied 316 stainless steel irradiated by electron/ion Production bias: a proposed modification of the driving
dual beams, S. Ohnuki, Y. Hidaka, H. Takahashi force for void swelling under cascade damage con-
and A. Hishinuma eae @ ec Ga + 6423 2.22 2 6:4 Oe 6 Oe ditions, C.H. Woo, B.N. Singh and F.A. Garner 1224
The influence of temperature on swelling behavior in
6.3. Point defect processes and evolution of microstructure electron irradiated austenitic stainless steels, J.P.
Qian, L.P. Lu, J.M. Chen, J.G. Sun and Z.Y. Zhao 1229
The control of point defect processes by the coherent- The effect of helium on microstructural evolution and
iron precipitates in copper alloys, /. Ishida 1139 mechanical properties of austenitic steels as deter-
Modeling the effects of damage rate and He /dpa ratio mined by spectral tailoring experiments, N.
on microstructural evolution, Y. Katoh, R.E. Stoller, Sekimura, F.A. Garner and R.D. Griffin
Fv Se a, SD ida 6's 4 ce bd es 1144 The influence of helium on mechanical properties of
A comparison of microstructures in copper irradiated model austenitic alloys, determined using >? Ni iso-
with fission, fusion and spallation neutrons, T. topic tailoring and fast reactor irradiation, M.L.
Muroga, H.L. Heinisch, W.F. Sommer and P.D. Fer- FOR Ge. GP give c icc crensecan 1239
guson 1150 Silicon’s role in determining swelling in neutron-irradi-
eae .6 O28 s. 6) &.- 6 iO 8'S°E. 61850 8- ER & OS'S O91 08'S
Fluctuation effect of point defect reaction on nucle- ated Fe—Ni-—Cr-Si alloys, N. Sekimura, F.A. Garner
ation of interstitial clusters during neutron irradia- and J.W. Newkirk
XVIil Contents
Cavity formation and growth during pulse high heat The effect of helium atoms on radiation-induced segre-
loading in nickel implanted with helium or deu- gation in nickel alloys, 7. Ezawa, E. Wakai, T.
terium ions, 7. Muroga, K. Dohi, Y. Ishihama, K. Tanabe and R. Oshima
Tokunaga and N. Yoshida Compositional behavior and stability of MC-type pre-
The influence of isotopically controlled boron addition cipitates in JPCA austenitic stainless steel during
on void swelling of nickel irradiated in FFTF, 7. HFIR irradiation, M. Suzuki, S. Hamada, P.J. Mazi-
Muroga and N. Yoshida asz, S. Jitsukawa and A. Hishinuma
Fission neutron irradiation of copper containing im- Microstructural phase stability of Cu-base alloys under
planted and transmutation produced helium, B.N. 300 keV Cu®* ion irradiation, N. Wanderka, Y.
Singh, A. Horsewell, M. Eldrup and F.A. Garner ... Yuan, L. Jiao, R.P. Wahi and H. Wollenberger 1356
Helium diffusion and bubble nucleation in the disloca-
tion core during irradiation, B.N. Singh and A.J.E.
Section 7. Radiation Facilities, Component Analysis and
Foreman
Component Tests
In-situ observation of the migration and growth of
helium bubbles in aluminum, K. Ono, S. Furuno, K.
Hojou, T. Kino, K. Izui, O. Takaoka, N. Kubo, K. Experimental facilities for investigation of structural
Mizuno and K. Ito material properties for fusion reactor under irradia-
On the statistical distribution of Cr atoms in Fe—Cr tion, G.M. Kalinin, Yu.S. Strebkov, A.V. Sidorenkou,
alloys with high swelling resistance in NFR, P. A.P. Zyryanov, V.I. Barsanov, V.V. Shushlebin, V.V.
Gondi, R. Montanari and R. Coppola Rybin, V.F. Vinokurov, N.B. Odintsov, V.A. Zykanov,
Computer simulation of fundamental features of a bias V.K. Shamardin and V.A. Kazakov
factor, E. Kuramoto Capability of energy selective neutron irradiation test
Coarsening of helium bubbles in FeCrNi measured by facility (ESNIT) for fusion reactor materials testing
small angle neutron scattering, F. Carsughi, W. and the status of ESNIT program, K. Noda, M.
Kesternich, D. Schwahn, H. Ullmaier and H. Sugimoto, Y. Kato, H. Matsuo, K. Watanabe, T.
Schroeder Kikuchi, H. Usui, Y. Oyama, H. Ohno and T. Kondo
The effect of ion irradiation on inert gas bubble mobil- Destruction of insulators in superconducting magnetic
ity, D.E. Alexander and R.C. Birtcher systems for use in thermonuclear reactors due to
Swelling and microstructure of high purity nickel irra- electrostatic charge under gamma and electron irra-
diated with fast neutrons in EBR-II, J.F. Stubbins diation, A.J. Akishin, Yu.I. Tutrin and A.G. Khorosh
and F.A. Garner Neutron flux enhancement at LASREF, W.F. Sommer,
A microstructural examination of the mechanical re- P.D. Ferguson and M.S. Wechsler
sponse of Fe—Cr--Ni alloys irradiated at 365°C us- Conceptual design of irradiation test facility for fusion
ing isotopic tailoring to produce different He /dpa blanket development, H. Sagawa, H. Kawamura, S.
ratios, J.F. Stubbins and F.A. Garner 1300 Shimakawa, H. Nabeya, M. Abe, T. Kurasawa, H.
Grain boundary cavities and cracks during high tem- Yoshida, Y. Ichihashi, I. Tanaka and Y. Futamura
perature irradiation embrittlement, V.A. Borodin, Comparison of measured and calculated transmutation
V.M. Manichev and A.I. Ryazanov in copper at spallation neutron sources, T.B.
A SIPA-based theory of irradiation creep in the low O’Hearn, A.S. Kumar and L.R. Greenwood
swelling rate regime, C.H. Woo and F.A. Garner Neutron and plasma irradiations of fusion reactor ma-
Observations of deuterium trapping in nickel irradi- terials using fusion plasma neutron sources, T.
ated by *He, 1. Takagi, H. Fujita, K. Shin and K. Kawabe, H. Yamaguchi, N. Mizuno, H. Sagawa, N.
Higashi Tachikawa and S. Hirayama
The influence of hydrogen on the formation of helium Damage of first wall materials of fusion reactor during
vacancy voids in metal, V.\V. Kirsanov, M.V. Musina plasma disruption, L./. Ivanov, V.N. Pimenov and
and V.V. Rybin J.M. Platov
The role of minor alloying elements in swelling of 316
steel, N. gata, T. Irino and A. Kohyama
Section 8. Materials Issues in Tokamak Test Machines and in
Study of He-bubble growth in MANET steel by small-
Near-Term Machines
angle neutron scattering, G. Albertini, F. Carsughi,
R. Coppola, W. Kesternich, G. Mercurio, F. Rus-
tichelli, D. Schwahn and H. Ullmaier Materials issues in diagnostic systems for BPX and
ITER, F.W. Clinard, Jr. E.H. Farnum, D.L.
6.5. Phase stability, diffusion and segregation Griscom, R.F. Mattas, S.S. Medley, F.W. Wiffen, S.S.
Wojtowicz, K.M. Young and S.J. Zinkle
Radiation-induced segregation in FFTF-irradiated Fatigue life assessment of 316L stainless steel and
austenitic stainless steels, E.A. Kenik and K. Hojou DIN-1.4914 martensitic steel before and after TEX-
Electron irradiation experiments in support of fusion TOR exposure, J.J. Shakib, H. Ullmaier, E.A. Little,
materials development, D.S. Gelles, §. Ohnuki, H. W. Schmitz, R.G. Faulkner and T.E. Chung
Takahashi, H. Matsui and Y. Kohno Fatigue crack growth in 316 type stainless steel at
Characteristics of point defects and their clustering temperatures and displacement damage rates rep-
processes in Fe-Mn-Cr and Fe-Mn-Si-Cr alloys, H. resentative for the first wall loading, P. Fenici and
Inoue, T. Muroga, Y. Miyamoto and N. Yoshida S. Suolang
Contents
A simple boronization technique for T-3M and T-11M Section 9. Low-activation Criteria
tokamak chambers, O./. Buzhinsky, E.A. Azizov,
A.M. Belov, S.A. Grashin, A.V. Krasilnikov, I.A. Ko-
Toward improved guidelines for reduced activation
van, C.V. Mirnov, A.A. Petrov, V.G. Petrov, D.V.
materials development in the US, D.G. Doran 1439
Portnov, T.S. Pulinets, A.N. Romannikov, A.A.
Production of high-purity vanadium, chromium and
Skvortsova, S.M. Sotnikov, S.N. Tugarinov, S.I. Fe-
titanium for use in low activation materials, D.
dorenko, A.P. Chernobaj, A.I. Kanaev, V.M. Shara-
Murphy and G.J. Butterworth .............0.5. 1444
pov, S.Y. Rybakov, A.E. Gorodetsky, A.P. Zakharov,
Low activation structural materials for ICF reactors:
A.A. Vasilyev, S.N. Luzganov, V.P. Fokin and A.N.
differences with MCF environments, J. Sanz, J.M.
eeee eee eee e r ee twee 1413
Perlado, A.S. Pérez and D. Guerra 1450
Test of the boron-containing coating of the graphite
Neutron activation of elements and the radiological
limiter in the T-10 tokamak, V.A. Barsuk, O.1.
implications for development and use of low activa-
Buzhinskiy, V.A. Vershkov, S.A. Grashin, V.M.
tion materials, G.M. Smith and G.J. Butterworth 1455
Gureev, M.I. Guseva, V.E. Neumoin, I.V. Opimach,
Environmental problems of application of iron as a
E.N. Kurolenkin, R.U. Mametiev, E.V. Tupizina and
base material of low activating steels for fusion and
V.N. Sharupin 1417
fission reactors, E.V. Dyomina, V.V. Ivanov, L.I.
Quality evaluation of graphites and carbon/ carbon
Ivanov, V.P. Kolotov and Yu.M. Platov 1461
composites during production of JT-60U plasma
Activation calculation for a tokamak engineering test
facing materials, 7. Ando, K. Kodama, M. Ya-
breeder, K.M. Feng 1464
mamoto, T. Arai, A. Kaminaga, H. Horiike, M. Eto,
Activation analyses for different fusion structural al-
K. Fukaya, T. Kiuchi, K. Teruyama, I. Nanai, S.
loys, H. Attaya and D. Smith 1469
Hanai, S. Ninomiya and M. Tezuka ............ 1423
Silicon carbide and the new low activation require-
Preliminary design study of the target and lithium
ments for a fusion reactor first wall, P. Rocco, H.W.
circulation system for ESNIT, Y. Kato, K. Watanabe
Scholz and M. Zucchetti
a sk een wee ae Cae ke eS 1428
Accelerator system for the energy selective neutron
irradiation test facility (ESNIT), M. Sugimoto, K. Author index
ee 6's £66 424A BCC ODDO HODES £00 6 2 8 OO
Noda, H. Ohno and T. Kondo Subject index
SOS. Oes8 € FO DGB LES 28H SE SE OEE OD