~ journaol f nuclear Journal of Nuclear Materials 187 (1992) 309-311 North-Holland pi, materials Author index Alexander, D.J., see Klueh, R.L. 187 (1992) 60 Chenier, M.P., see Elliot, A.J. 187 (1992) 230 Alimov, V.Kh., R. Schworer, B.M.U. Choudhury, R., see Das, P. 187 (1992) 272 Scherzer and J. Roth, Thermal desorp- Christensen, L.D., see Emig, J.A. 187 (1992) 209 tion of D, and CD, from bulk-boronized Coronado, P.R., see Emig, J.A. 187 (1992) 209 graphites 187 (1992) 191 Asari, E., see Nakamura, K.G. 187 (1992) 294 Daiev, Ch., see Vassilev, G.P. 187 (1992) 99 Asundi, M.K., see Chakravartty, J.K. 187 (1992) 260 Daimon, T., see Miyake, M. 187 (1992) 138 Axler, K.M. and R.I. Sheldon, The effect of Das, P. and R. Choudhury, Formation of initial composition on PuOCl formation peripheral porosity regions around ura- in the direct oxide reduction of PuO, 187 (1992) 183 nia in zirconia—urania mixed oxide pow- der compact sintering 187 (1992) 272 Bai, J.B. and D. Francois, Some evidence of Dey, G.K., see Kishore, R. 187 (1992) 70 a brittle—ductile transition of zirconium Duclos, A.M., see Hayward, P.J. 187 (1992) 215 hydride between 20 and 350°C 187 (1992) 186 Balasubramaniam, R., Elastic moduli of bi- Elliot, A.J. and M.P. Chenier, Radiolysis of 4.5 mol dm~* LiOH with °Li(n, a)°H nary bcc solid solutions of Group Vb elements 187 (1992) 180 ion recoil 187 (1992) 230 Bandurko, V.V., see Pisarev, A.A. 187 (1992) 254 Emig, J.A., R.G. Garza, L.D. Christensen, Banerjee, S., see Chakravartty, J.K. 187 (1992) 260 P.R. Coronado and P.C. Souers, Helium Barabash, V.R., A.G. Baranov, J. Gahl, V.L. release from 19-year-old palladium tri- Litunovsky, J. McDonald and _ I.B. tide 187 (1992) 209 Ovchinnikov, Experimental study of pulse Evans, D.G., see Hayward, P.J. 187 (1992) 215 plasma-—carbon materials interaction dur- ing the simulation of thermal quench Federici, G., C.H. Wu, A.R. Raffray and phase of tokamak plasma disruption 187 (1992) 298 M.C. Billone, Modeling of tritium release Baranov, A.G., see Barabash, V.R. 187 (1992) 298 from ceramic breeders: Status and some Bardon, J., see Grisolia, C. 187 (1992) 74 implications for next-step devices 187 (1992) 1 Bell, G.E.C., T. Inazumi, E.A. Kenik and T. Forlerer de Svarch, E., see Rodriguez, C. 187 (1992) 97 Kondo, Electrochemical and microstruc- Francois, D., see Bai, J.B. 187 (1992) 186 tural characterization of an austenitic Fujii, K., H. Imai, S. Nomura and M. Shindo, stainless steel irradiated by heavy ions at Functionally gradient material of silicon 515°C 187 (1992) 170 carbide and carbon as advanced oxida- Billone, M.C., see Federici, G. 187(1992) 1 tion-resistant graphite 187 (1992) 204 Boivin, R. and B. Terreault, Laser desorp- Fujii, K., S. Nomura, H. Imai and M. Shindo, tion study of beryllium’s hydrogen recy- Oxidation behavior of boronated graphite cling properties at high temperature 187 (1992) 117 in helium, containing water vapor 187 (1992) 32 Borodin, V.A., Yu.R. Kevorkyan, V.V. Kolomytkin and A.I. Ryazanov, An esti- Gahl, J., see Barabash, V.R. 187 (1992) 298 mate of the irradiation creep rate in a-Fe Garner, F.A. and M.A. Mitchell, The com- based on computer simulation of vacancy plex role of phosphorus in the neutron- pipe diffusion along <100){010} disloca- induced swelling of titanium-modified tions 187 (1992) 131 austenitic stainless steels 187 (1992) 223 Britz, L., see Ghoneim, M.M. 187 (1992) 80 Garner, F.A., see Mitchell, M.A. 187 (1992) 103 Garza, R.G., see Emig, J.A. 187 (1992) 209 Chakravartty, J.K., S. Banerjee, Y.V.R.K. George, I.M., see Hayward, P.J. 187 (1992) 215 Prasad and M.K. Asundi, Hot-working Ghoneim, M.M., F.H. Hammad, D. Pachur characteristics of Zircaloy-2 in the tem- and L. Britz, Compound Charpy speci- perature range of 650-—950°C 187 (1992) 260 mens by adhesive joining 187 (1992) 80 310 Author index Grisolia, C., A. Grosman and J. Bardon, Mitchell, M.A. and F.A. Garner, Neutron- Depletion of hydrogenoid atoms from the induced swelling of binary Ni—Al alloys 187 (1992) 103 carbonized layer in Tore Supra 187 (1992) 74 Mitchell, M.A., see Garner, F.A. 187 (1992) 223 Grosman, A., see Grisolia, C. 187 (1992) 74 Miyake, C., see Miyake, M. 187 (1992) 138 Miyake, M., W. Saiki, T. Daimon, P. Son, C. Hamilton, M.L., see Huang, F.H. 187 (1992) 278 Miyake and H. Ohya-Nishiguchi, ESR Hammad, F.H., see Ghoneim, M.M. 187 (1992) 80 spectra in graphite irradiated with He~ Hashimoto, T. and N. Shigenaka, A theory ions 187 (1992) 138 of dislocation loop formation in binary Munakata, K., see Nishikawa, M. 187 (1992) 153 alloys under irradiation 187 (1992) 161 Hayward, P.J., D.G. Evans, P. Taylor, I.M. Nagai, S., see Terai, T. 187 (1992) 247 George and A.M. Duclos, Oxidation of Nakamura, K.G., E. Asari, M. Kitajima and uranium in argon—25% oxygen at 190- T. Kawabe, The energy dependence of 610°C 187 (19922)1 5 lattice damage in graphite induced by Hishinuma, A., see Sawai, T. 187 (1992) 146 low energy He-ion irradiation 187 (1992) 294 Huang, F.H. and M.L. Hamilton, The frac- Nishikawa, M., Y. Kawamura, K. Munakata ture toughness database of ferritic alloys and K. Yoneda, Li transfer from a Li,O irradiated to very high neutron exposures 187 (1992) 278 blanket 187 (1992) 153 Nomura, S., see Fujii, K. 187 (1992) 204 Imai, H., see Fujii, K. 187 (1992) 204 Nomura, S., see Fujii, K. 187 (1992) 32 Imai, H., see Fujii, K. 187 (1992) 32 Inazumi, T., see Bell, G.E.C. 187 (1992) 170 Ohya-Nishiguchi, H., see Miyake, M. 187 (1992) 138 Olander, D.R., see Park, K. 187 (1992) 89 Kanashenko, S.L. and D.B. Kuzminov, Ovchinnikov, I.B., see Barabash, V.R. 187 (1992) 298 Phase-equilibrium diagram for heavy in- ert gas bubbles confined in an elastic Pachur, D., see Ghoneim, M.M. 187 (1992) 80 matrix 187 (1992) 55 Park, K. and D.R. Olander, Defect models Kawabe, T., see Nakamura, K.G. 187 (1992) 294 for the oxygen potentials of gadolinium- Kawamura, Y., see Nishikawa, M. 187 (1992) 153 and europium-doped urania 187 (1992) 89 Kenik, E.A., Radiation-induced segregation Patil, R.V., Self-diffusion in Zr—Ag alloys 187 (1992) 197 in irradiated Type 304 stainless steels 187 (1992) 239 Pisarev, A.A., V.M. Smirnov, S.K. Zhdanov, Kenik, E.A., see Bell, G.E.C. 187 (1992) 170 A.V. Varava and V.V. Bandurko, Trap- Kevorkyan, Yu.R., see Borodin, V.A. 187 (1992) 131 ping and reemission of deuterium im- Kinoshita, C., see Yasuda, K. 187 (1992) 109 planted in BN 187 (1992) 254 Kishore, R., R.N. Singh, G.K. Dey and T.K. Prasad, Y.V.R.K., see Chakravartty, J.K. 187 (1992) 260 Sinha, Age hardening of cold-worked Pulham, R.J. and M.W. Richards, Chemical Zr-—2.5wt% Nb pressure tube alloy 187 (1992) 70 reactions of caesium, tellurium and oxy- Kitajima, M., see Nakamura, K.G. 187 (1992) 294 gen with fast breeder reactor cladding Klueh, R.L. and D.J. Alexander, Embrittle- alloys. Part V - The corrosion of ment of 9Cr—-IMoVNb and = 12Cr- 12R72HV steel by Cs,Te under constant IMoVW steels irradiated in HFIR 187 (1992) 60 O, potentials 187 (1992) 39 Klueh, R.L. and P.J. Maziasz, Effect of irra- diation in HFIR on tensile properties of Cr—Mo steels 187 (1992) 43 Raffray, A.R., see Federici, G. 187(1992) 1 Kolomytkin, V.V., see Borodin, V.A. 187 (1992) 131 Richards, M.W., see Pulham, R.J. 187 (1992) 39 Kondo, T., see Bell, G.E.C. 187 (1992) 170 Rodriguez, C. and E. Forlerer de Svarch, Kutsuwada, M., see Yasuda, K. 187 (1992) 109 The influence of iron impurities on grain Kuzminov, D.B., see Kanashenko, S.L. 187 (1992) 55 boundary self-diffusion in zirconium be- low 1138 K 187 (1992) 97 Lemaignan, C., Impact of B~ radiolysis and Roth, J., see Alimov, V.Kh. 187 (1992) 191 transient products on_ irradiation-en- Ryazanov, A.I., see Borodin, V.A. 187 (1992) 131 hanced corrosion of zirconium alloys 187 (1992) 122 Litunovsky, V.L., see Barabash, V.R. 187 (1992) 298 Saiki, W., see Miyake, M. 187 (1992) 138 Sawai, T., M. Suzuki, P.J. Maziasz and A. Maziasz, P.J., see Klueh, R.L. 187 (1992) 43 Hishinuma, Comparison of immersion Maziasz, P.J., see Sawai, T. 187 (1992) 146 density and improved microstructural McDonald, J., see Barabash, V.R. 187 (19922)9 8 characterization methods for measuring Author index swelling in small irradiated disk speci- Takahashi, Diffusion coefficient of tri- mens 187 (1992) 146 tium in molten lithium-lead alloy Scherzer, B.M.U., see Alimov, V.Kh. 187 (1992) 191 (Li,;Pb,;) under neutron irradiation at Schworer, R., see Alimov, V.Kh. 187 (1992) 191 elevated temperatures 187 (1992) 247 Shaikh, M.A., Void denudation and grain Terreault, B., see Boivin, R. 187 (1992) 117 boundary migration in ion-irradiated nickel 187 (19923)0 3 Varava, A.V., see Pisarev, A.A. 187 (1992) 254 Sheldon, R.I., see Axler, K.M. 187 (19921)8 3 Vassilev, G.P. and Ch. Daiev, Alkaline solu- Shigenaka, N., see Hashimoto, T. 187 (19921)6 1 tions—bitumen interactions 187 (1992) 99 Shindo, M., see Fujii, K. 187 (19922)0 4 Shindo, M., see Fujii, K. 187 (1992) 32 Wu, C.H., see Federici, G. 187 (1992) 1 Shinohara, K., see Yasuda, K. 187 (19921)0 9 Singh, R.N., see Kishore, R. 187 (1992) 70 Yamada, M., see Yasuda, K. 187 (1992) 109 Sinha, T.K., see Kishore, R. 187 (1992) 70 Yasuda, K., K. Shinohara, M. Yamada, M. Smirnov, V.M., see Pisarev, A.A. 187 (19922)5 4 Kutsuwada and C. Kinoshita, A new Son, P., see Miyake, M. 187 (19921)3 8 method for evaluating stress-strain prop- Souers, P.C., see Emig, J.A. 187 (19922)0 9 erties of metals using ultra-microhard- Suzuki, M., see Sawai, T. 187 (19921)4 6 ness technique 187 (1992) 109 Yoneda, K., see Nishikawa, M. 187 (1992) 153 Takahashi, Y., see Terai, T. 187 (19922)4 7 Yoneoka, T., see Terai, T. 187 (1992) 247 Taylor, P., see Hayward, P.J. 187 (19922)1 5 Terai, T., S. Nagai, T. Yoneoka and Y. Zhdanov, S.K., see Pisarev, A.A. 187 (19922)5 4 journal of nuclear Journal of Nuclear Materials 187 (1992) 313-317 North-Holland materials Subject index alloys. Part V -—- The corrosion of Alloys and Metals (“Various”, i.e. not listed elsewhere by 12R72HV steel by Cs,Te under constant name) O, potentials, R.J. Pulham and M.W. A theory of dislocation loop formation in Richards 187 (1992) 39 binary alloys under irradiation, T. Hashimoto and N. Shigenaka 187 (1992) 161 Compatibility and Corrosion Oxidation behavior of boronated graphite in Analytical Instruments and Methods helium, containing water vapor, K. Fujii, The energy dependence of lattice damage in S. Nomura, H. Imai and M. Shindo 187 (1992) 32 graphite induced by low energy He-ion Chemical reactions of caesium, tellurium and irradiation, K.G. Nakamura, E. Asari, M. oxygen with fast breeder reactor cladding Kitajima and T. Kawabe 187 (1992) 294 alloys. Part V -—- The corrosion of 12R72HV steel by Cs,Te under constant Beryllium, Beryllium Alloys and Compounds O, potentials, R.J. Pulham and M.W. Laser desorption study of beryllium’s hydro- Richards 187 (1992) 39 gen recycling properties at high tempera- Alkaline solutions—bitumen interactions, ture, R. Boivin and B. Terreault 187 (1992) 117 G.P. Vassilev and Ch. Daiev 187 (1992) 99 Trapping and reemission of deuterium im- Impact of B~ radiolysis and transient prod- planted in BN, A.A. Pisarev, V.M. ucts on irradiation-enhanced corrosion of Smirnov, S.K. Zhdanov, A.V. Varava and zirconium alloys, C. Lemaignan 187 (1992) 122 V.V. Bandurko 187 (1992) 254 Electrochemical and microstructural charac- terization of an austenitic stainless steel Blanket Materials irradiated by heavy ions at 515°C, G.E.C. Modeling of tritium release from ceramic Bell, T. Inazumi, E.A. Kenik and T. breeders: Status and some implications Kondo 187 (1992) 170 for next-step devices, G. Federici, C.H. Oxidation of uranium in argon—25% oxygen Wu, A.R. Raffray and M.C. Billone 187(1992) 1 at 190-610°C, P.J. Hayward, D.G. Evans, Li transfer from a Li,O blanket, M. P. Taylor, I.M. George and A.M. Duclos 187 (19922)1 5 Nishikawa, Y. Kawamura, K. Munakata and K. Yoneda 187 (1992) 153 Computer Calculations, including Modelling Radiolysis of 4.5 mol dm~* LiOH with °Li(n, w)°H ion recoil, A.J. Elliot and Modeling of tritium release from ceramic M.P. Chenier 187 (1992) 230 breeders: Status and some implications for next-step devices, G. Federici, C.H. Diffusion coefficient of tritium in molten Wu, A.R. Raffray and M.C. Billone 187(1992) 1 lithium-—lead alloy (Li,;Pb,,) under neu- An estimate of the irradiation creep rate in tron irradiation at elevated temperatures, a-Fe based on computer simulation of T. Terai, S. Nagai, T. Yoneoka and Y. vacancy pipe diffusion along <100){010} Takahashi 187 (1992) 247 dislocations, V.A. Borodin, Yu.R. Kevor- kyan, V.V. Kolomytkin and A.I. Ryazanov 187 (1992) 131 Ceramics (“Various”, i.e. not listed elsewhere by name) A theory of dislocation loop formation in Thermal desorption of D, and CD, from binary alloys under irradiation, T. Hashi- bulk-boronized graphites, V.Kh. Alimov, moto and N. Shigenaka 187 (1992) 161 R. Schworer, B.M.U. Scherzer and J. Roth 187 (1992) 191 Creep and Relaxation Cladding Materials An estimate of the irradiation creep rate in Chemical reactions of caesium, tellurium and a-Fe based on computer simulation of oxygen with fast breeder reactor cladding vacancy pipe diffusion along <100>{010} 314 Subject index dislocations, V.A. Borodin, Yu.R. Kevor- resistant graphite, K. Fujii, H. Imai, S. kyan, V.V. Kolomytkin and A.]. Ryazanov 187 (1992) 131 Nomura and M. Shindo 187 (1992) 204 Defects and Defect Structures Fast Reactors Defect models for the oxygen potentials of Chemical reactions of caesium, tellurium and gadolinium- and europium-doped urania, oxygen with fast breeder reactor cladding K. Park and D.R. Olander 187 (1992) 89 alloys. Part V -—-— The corrosion of An estimate of the irradiation creep rate in 12R72HV steel by Cs,Te under constant a-Fe based on computer simulation of O, potentials, R.J. Pulham and M.W. vacancy pipe diffusion along <100){010} Richards 187 (1992) 39 dislocations, V.A. Borodin, Yu.R. Kevor- The complex role of phosphorus in the neu- kyan, V.V. Kolomytkin and A.I. Ryazanov 187 (1992) 131 tron-induced swelling of titanium-mod- A theory of dislocation loop formation in ified austenitic stainless steels, F.A. Gar- binary alloys under irradiation, T. ner and M.A. Mitchell 187 (1992) 223 Hashimoto and N. Shigenaka 187 (1992) 161 Void denudation and grain boundary migra- Fracture and Fracture Toughness tion in ion-irradiated nickel, M.A. Shaikh 187 (1992) 303 Embrittlement of 9Cr—l1MoVNb and 12Cr- IMoVW steels irradiated in HFIR, R.L. Diffusion (incl. Thermodiffusion) Klueh and D.J. Alexander 187 (1992) 60 The influence of iron impurities on grain Compound Charpy specimens by adhesive boundary self-diffusion in zirconium be- joining, M.M. Ghoneim, F.H. Hammad, low 1138 K, C. Rodriguez and E. For- D. Pachur and L. Britz 187 (1992) 80 lerer de Svarch 187 (1992) 97 Some evidence of a brittle—ductile transition Self-diffusion in Zr—Ag alloys, R.V. Patil 187 (1992) 197 of zirconium hydride between 20 and Diffusion coefficient of tritium in molten 350°C, J.B. Bai and D. Frangois 187 (1992) 186 lithium—lead alloy (Li,;Pb,,) under neu- The fracture toughness database of ferritic tron irradiation at elevated temperatures, alloys irradiated to very high neutron ex- T. Terai, S. Nagai, T. Yoneoka and Y. posures, F.H. Huang and M.L. Hamilton 187 (1992) 278 Takahashi 187 (1992) 247 Fuels and Fuel Elements Divertor The effect of initial composition on PuOCl Experimental study of pulse plasma—carbon formation in the direct oxide reduction of materials interaction during the simula- PuO,, K.M. Axler and R.I. Sheldon 187 (1992) 183 tion of thermal quench phase of tokamak plasma disruption, V.R. Barabash, A.G. Fusion Reactors Baranov, J. Gahl, V.L. Litunovsky, J. Mc- Modeling of tritium release from ceramic Donald and I1.B. Ovchinnikov 187 (1992) 298 breeders: Status and some implications for next-step devices, G. Federici, C.H. Electron Microscopy and Electron Probe Microanalysis Wu, A.R. Raffray and M.C. Billone 187(1992) 1 Comparison of immersion density and im- Depletion of hydrogenoid atoms from the proved microstructural characterization carbonized layer in Tore Supra, C. Griso- methods for measuring swelling in small lia, A. Grosman and J. Bardon 187 (1992) 74 irradiated disk specimens, T. Sawai, M. Li transfer from a Li,O blanket, M. Suzuki, P.J. Maziasz and A. Hishinuma 187 (1992) 146 Nishikawa, Y. Kawamura, K. Munakata Radiation-induced segregation in irradiated and K. Yoneda 187 (1992) 153 Type 304 stainless steels, E.A. Kenik 187 (1992) 239 Radiolysis of 4.5 mol dm~* LiOH with °Li(n, a)°H ion recoil, A.J. Elliot and Experimental Techniques M.P. Chenier 187 (1992) 230 A new method for evaluating stress—strain properties of metals using ultra-micro- Gases (excl. Hydrogen, Helium and Tritium) in Metals, Alloys hardness technique, K. Yasuda, K. Shi- and Ceramics nohara, M. Yamada, M. Kutsuwada and Phase-equilibrium diagram for heavy inert C. Kinoshita 187 (1992) 109 gas bubbles confined in an elastic matrix, S.L. Kanashenko and D.B. Kuzminov 187 (1992) 55 Fabrication Functionally gradient material of silicon car- Graphite and Carbon bide and carbon as advanced oxidation- Oxidation behavior of boronated graphite in Subject index helium, containing water vapor, K. Fujii, Helium release from 19-year-old palladium S. Nomura, H. Imai and M. Shindo 187 (1992) 32 tritide, J.A. Emig, R.G. Garza, L.D. Depletion of hydrogenoid atoms from the Christensen, P.R. Coronado and P.C. carbonized layer in Tore Supra, C. Griso- Souers 187 (1992) 209 lia, A. Grosman and J. Bardon 187 (1992) 74 Radiolysis of 4.5 mol dm~* LiOH with ESR spectra in graphite irradiated with He ~ °Li(n, a)°H ion recoil, A.J. Elliot and ions, M. Miyake, W. Saiki, T. Daimon, P. M.P. Chenier 187 (1992) 230 Son, C. Miyake and H. Ohya-Nishiguchi 187 (1992) 138 Trapping and reemission of deuterium im- Thermal desorption of D, and CD, from planted in BN, A.A. Pisarev, V.M. bulk-boronized graphites, V.Kh. Alimov, Smirnov, S.K. Zhdanov, A.V. Varava and R. Schworer, B.M.U. Scherzer and J. V.V. Bandurko 187 (1992) 254 Roth 187 (1992) 191 Functionally gradient material of silicon car- Impurities bide and carbon as advanced oxidation- The influence of iron impurities on grain resistant graphite, K. Fujii, H. Imai, S. boundary self-diffusion in zirconium be- Nomura and M. Shindo 187 (1992) 204 low 1138 K, C. Rodriguez and E. For- The energy dependence of lattice damage in lerer de Svarch 187 (1992) 97 graphite induced by low energy He-ion irradiation, K.G. Nakamura, E. Asari, M. Irradiation Effects (excl. Defects, Swelling and Voids) Kitajima and T. Kawabe 187 (1992) 294 Effect of irradiation in HFIR on tensile Experimental study of pulse plasma—carbon properties of Cr—Mo steels, R.L. Klueh materials interaction during the simula- and P.J. Maziasz 187 (1992) 43 tion of thermal quench phase of tokamak Embrittlement of 9Cr—1MoVNb and 12Cr- plasma disruption, V.R. Barabash, A.G. IMoVW steels irradiated in HFIR, R.L. Baranov, J. Gahl, V.L. Litunovsky, J. Mc- Klueh and D.J. Alexander 187 (1992) 60 Donald and I.B. Ovchinnikov 187 (1992) 298 Compound Charpy specimens by adhesive joining, M.M. Ghoneim, F.H. Hammad, D. Pachur and L. Britz 187 (1992) 80 Helium Impact of B~ radiolysis and transient prod- Effect of irradiation in HFIR on tensile ucts on irradiation-enhanced corrosion of properties of Cr—Mo steels, R.L. Klueh and P.J. Maziasz 187 (1992) 43 zirconium alloys, C. Lemaignan 187 (1992) 122 ESR spectra in graphite irradiated with He * Helium release from 19-year-old palladium ions, M. Miyake, W. Saiki, T. Daimon, P. tritide, J.A. Emig, R.G. Garza, L.D. Son, C. Miyake and H. Ohya-Nishiguchi 187 (1992) 138 Christensen, P.R. Coronado and P.C. Souers 187 (1992) 209 A theory of dislocation loop formation in binary alloys under irradiation, T. The energy dependence of lattice damage in Hashimoto and N. Shigenaka 187 (1992) 161 graphite induced by low energy He-ion irradiation, K.G. Nakamura, E. Asari, M. Diffusion coefficient of tritium in molten lithium-lead alloy (Li,7Pb,,) under neu- Kitajima and T. Kawabe 187 (1992) 294 tron irradiation at elevated temperatures, T. Terai, S. Nagai, T. Yoneoka and Y. High-Temperature Reactors Takahashi 187 (19922)4 7 Oxidation behavior of boronated graphite in The fracture toughness database of ferritic helium, containing water vapor, K. Fujii, alloys irradiated to very high neutron ex- S. Nomura, H. Imai and M. Shindo 187 (1992) 32 posures, F.H. Huang and M.L. Hamilton 187 (1992) 278 The energy dependence of lattice damage in Hydrogen and Hydrides (incl. Deuterium and Deuterides) graphite induced by low energy He-ion Depletion of hydrogenoid atoms from the irradiation, K.G. Nakamura, E. Asari, M. carbonized layer in Tore Supra, C. Griso- Kitajima and T. Kawabe 187 (1992) 294 lia, A. Grosman and J. Bardon 187 (1992) 74 Laser desorption study of beryllium’s hydro- Kinetics gen recycling properties at high tempera- Oxidation behavior of boronated graphite in ture, R. Boivin and B. Terreault 187 (1992) 117 helium, containing water vapor, K. Fujii, Thermal desorption of D, and CD, from S. Nomura, H. Imai and M. Shindo 187 (1992) 32 bulk-boronized graphites, V.Kh. Alimov, Depletion of hydrogenoid atoms from the R. Schworer, B.M.U. Scherzer and J. carbonized layer in Tore Supra, C. Griso- Roth 187 (1992) 191 lia, A. Grosman and J. Bardon 187 (1992) 74 316 Subject index Alkaline solutions—bitumen interactions, Plutonium, Plutonium Alloys and Compounds G.P. Vassilev and Ch. Daiev 187 (1992) 99 The effect of initial composition on PuOCl A theory of dislocation loop formation in formation in the direct oxide reduction of binary alloys under irradiation, T. PuO,, K.M. Axler and R.I. Sheldon 187 (1992) 183 Hashimoto and N. Shigenaka 187 (1992) 161 Pore Behaviour and Porosity Liquid Metals Formation of peripheral porosity regions Diffusion coefficient of tritium in molten around urania in zirconia—urania mixed lithium-lead alloy (Li,;Pb,,) under neu- oxide powder compact sintering, P. Das tron irradiation at elevated temperatures, and R. Choudhury 187 (1992) 272 T. Terai, S. Nagai, T. Yoneoka and Y. Takahashi 187 (1992) 247 Powder Processes and Products Formation of peripheral porosity regions around urania in zirconia—urania mixed Mechanical Properties (‘‘Various’’, i.e. not listed elsewhere by oxide powder compact sintering, P. Das name) and R. Choudhury 187 (1992) 272 Age hardening of cold-worked Zr-—2.5wt% Nb pressure tube alloy, R. Kishore, R.N. Singh, G.K. Dey and T.K. Sinha 187 (1992) 70 Refractory Metals and Alloys (‘“Various’’, i.e. not listed else- where by name) A new method for evaluating stress—strain Elastic moduli of binary bec solid solutions properties of metals using ultra-micro- of Group Vb elements, R. Balasubrama- hardness technique, K. Yasuda, K. Shi- niam 187 (1992) 180 nohara, M. Yamada, M. Kutsuwada and C. Kinoshita 187 (1992) 109 Segregation Elastic moduli of binary bcc solid solutions Neutron-induced swelling of binary Ni-—Al of Group Vb elements, R. Balasubrama- alloys, M.A. Mitchell and F.A. Garner 187 (1992) 103 niam 187 (1992) 180 Radiation-induced segregation in irradiated Hot-working characteristics of Zircaloy-2 in Type 304 stainless steels, E.A. Kenik 187 (1992) 239 the temperature range of 650-—950°C, J.K. Chakravartty, S. Banerjee, Y.V.R.K. Prasad and M.K. Asundi 187 (1992) 260 Silicon Refractory Ceramics Functionally gradient material of silicon car- bide and carbon as advanced oxidation- Microstructure (incl. Textures) resistant graphite, K. Fujii, H. Imai, S. Electrochemical and microstructural charac- Nomura and M. Shindo 187 (1992) 204 terization of an austenitic stainless steel irradiated by heavy ions at 515°C, G.E.C. Steels Bell, T. Inazumi, E.A. Kenik and T. Effect of irradiation in HFIR on tensile Kondo 187 (1992) 170 properties of Cr—Mo steels, R.L. Klueh and P.J. Maziasz 187 (1992) 43 Nickel and Nickel Alloys Embrittlement of 9Cr—1MoVNb and 12Cr- Neutron-induced swelling of binary Ni-—Al IMoVW steels irradiated in HFIR, R.L. alloys, M.A. Mitchell and F.A. Garner 187 (1992) 103 Klueh and D.J. Alexander 187 (1992) 60 Void denudation and grain boundary migra- Compound Charpy specimens by adhesive tion in ion-irradiated nickel, M.A. Shaikh 187 (1992) 303 joining, M.M. Ghoneim, F.H. Hammad, D. Pachur and L. Britz 187 (1992) 80 Phase Transformation Comparison of immersion density and im- Phase-equilibrium diagram for heavy inert proved microstructural characterization gas bubbles confined in an elastic matrix, methods for measuring swelling in small S.L. Kanashenko and D.B. Kuzminov 187 (1992) 55 irradiated disk specimens, T. Sawai, M. Suzuki, P.J. Maziasz and A. Hishinuma 187 (1992) 146 Plasma Disruption Electrochemical and microstructural charac- Experimental study of pulse plasma—carbon terization of an austenitic stainless steel materials interaction during the simula- irradiated by heavy ions at 515°C, G.E.C. tion of thermal quench phase of tokamak Bell, T. Inazumi, E.A. Kenik and T. plasma disruption, V.R. Barabash, A.G. Kondo 187 (1992) 170 Baranov, J. Gahl, V.L. Litunovsky, J. Mc- The complex role of phosphorus in the neu- Donald and I.B. Ovchinnikov 187 (1992) 298 tron-induced swelling of titanium-mod- Subject index ified austenitic stainless steels, F.A. Gar- for next-step devices, G. Federici, C.H. ner and M.A. Mitchell 187 (1992) 223 Wu, A.R. Raffray and M.C. Billone 187(1992) 1 Radiation-induced segregation in irradiated Helium release from 19-year-old palladium Type 304 stainless steels, E.A. Kenik 187 (1992) 239 tritide, J.A. Emig, R.G. Garza, L.D. The fracture toughness database of ferritic Christensen, P.R. Coronado and P.C. alloys irradiated to very high neutron ex- Souers 187 (1992) 209 posures, F.H. Huang and M.L. Hamilton 187 (1992) 278 Diffusion coefficient of tritium in molten lithium-lead alloy (Li,7Pb,,) under neu- Strenght Properties tron irradiation at elevated temperatures, Effect of irradiation in HFIR on tensile T. Terai, S. Nagai, T. Yoneoka and Y. properties of Cr—Mo steels, R.L. Klueh Takahashi 187 (1992) 247 and P.J. Maziasz 187 (1992) 43 Surface Effects and Characterization Techniques Uranium and Uranium Alloys ESR spectra in graphite irradiated with He * Oxidation of uranium in argon—25% oxygen ions, M. Miyake, W. Saiki, T. Daimon, P. at 190-610°C, P.J. Hayward, D.G. Evans, Son, C. Miyake and H. Ohya-Nishiguchi 187 (1992) 138 P. Taylor, I.M. George and A.M. Duclos 187 (1992) 215 Thermal desorption of D, and CD, from bulk-boronized graphites, V.Kh. Alimov, Uranium Ceramics R. Schworer, B.M.U. Scherzer and J. Defect models for the oxygen potentials of Roth 187 (1992) 191 gadolinium- and europium-doped urania, K. Park and D.R. Olander 187 (1992) 89 Swelling Oxidation of uranium in argon—25% oxygen Neutron-induced swelling of binary Ni-—Al at 190-610°C, P.J. Hayward, D.G. Evans, alloys, M.A. Mitchell and F.A. Garner 187 (1992) 103 P. Taylor, I.M. George and A.M. Duclos 187 (19922)1 5 Comparison of immersion density and im- Formation of peripheral porosity regions proved microstructural characterization around urania in zirconia—urania mixed methods for measuring swelling in small oxide powder compact sintering, P. Das irradiated disk specimens, T. Sawai, M. and R. Choudhury 187 (1992) 272 Suzuki, P.J. Maziasz and A. Hishinuma 187 (1992) 146 The complex role of phosphorus in the neu- Wastes (radioactive) tron-induced swelling of titanium-mod- Alkaline solutions—bitumen interactions, ified austenitic stainless steels, F.A. Gar- ner and M.A. Mitchell 187 (1992) 223 G.P. Vassilev and Ch. Daiev 187 (1992) 99 Thermal Reactors Zirconium, Zirconium Alloys and Compounds Oxidation of uranium in argon—25% oxygen Age hardening of cold-worked Zr-—2.5wt% at 190-610°C, P.J. Hayward, D.G. Evans, Nb pressure tube alloy, R. Kishore, R.N. P. Taylor, I.M. George and A.M. Duclos 187 (19922)1 5 Singh, G.K. Dey and T.K. Sinha 187 (1992) 70 The influence of iron impurities on grain Thermodynamic Properties boundary self-diffusion in zirconium be- Phase-equilibrium diagram for heavy inert low 1138 K, C. Rodriguez and E. For- gas bubbles confined in an elastic matrix, lerer de Svarch 187 (1992) 97 S.L. Kanashenko and D.B. Kuzminov 187 (1992) 55 Impact of B~ radiolysis and transient prod- Li transfer from a Li,O blanket, M. ucts on irradiation-enhanced corrosion of Nishikawa, Y. Kawamura, K. Munakata zirconium alloys, C. Lemaignan 187 (1992) 122 and K. Yoneda 187 (1992) 153 Some evidence of a brittle—ductile transition The effect of initial composition on PuOCl of zirconium hydride between 20 and formation in the direct oxide reduction of 350°C, J.B. Bai and D. Frangois 187 (1992) 186 PuO,, K.M. Axler and R.I. Sheldon 187 (1992) 183 Self-diffusion in Zr—Ag alloys, R.V. Patil 187 (1992) 197 Hot-working characteristics of Zircaloy-2 in Thermophysical Properties the temperature range of 650-—950°C, J.K. Defect models for the oxygen potentials of Chakravartty, S. Banerjee, Y.V.R.K. gadolinium- and europium-doped urania, Prasad and M.K. Asundi 187 (1992) 260 K. Park and D.R. Olander 187 (1992) 89 Formation of peripheral porosity regions Tritium and Tritides around urania in zirconia—urania mixed Modeling of tritium release from ceramic oxide powder compact sintering, P. Das breeders: Status and some implications and R. Choudhury 187 (1992) 272