Nuclear Engineering and Design 1991: Vol 131 Index

5 Pages·1991·0.97 MB·English

Nuclear Engineering and Design 131 (1991) 347-348 347
North-Holland
Author Index to Volume 131
Almenas, K., C.C. Wu, L. Ragulskis and M. including accident management mea-
diMarzo, An unstable, condensation con- sures 131 (1991) 129
trolled two-phase natural circulation Goll, W., see Walker, C.T. 131 (1991) 1
mode 131 (1991) 241
Altac, Z. and N. Yucel, An investigation for Hohmann, H., see Birger, M. 131 (1991) 61
usage of graphite powder-helium suspen-
sion as reactor coolant ina HTGR 131 (1991) 71
Jost, $.D. and Y.L. Mo, An algorithm for
Anoda, Y., see Kukita, Y. 131 (1991) 101
seismic analysis of low-rise structural
Aya, I. and H. Nariai, Evaluation of heat-
walls 131 (1991) 263
transfer coefficient at direct-contact con-
densation of cold water and steam 131 (1991) 17
Kataoka, S., see Yoshida, K. 131 (1991) 337
Kelly, D.L., Overview of containment vent-
Bridgeman, J. and R. Shankar, Erosion /cor-
ing as an accident mitigation strategy in
rosion data handling for reliable NDE 131 (1991) 285
US light water reactors 131 (1991) 253
Brocks, W., see Yuan, H. 131 (1991) 157
Khan, S.A., Reliability assessment of emer-
Buck, M., see Burger, M. 131 (1991) 61
gency exhaust system in a pool-type re-
Burger, M., K. Miller, M. Buck, S.-H. Cho, search reactor 131 (1991) 37
A. Schatz, H. Schins, R. Zeyen and H.
Kukita, Y., Y. Anoda and K. Tasaka, Sum-
Hohmann, Examination of thermal deto-
mary of ROSA-IV LSTF first-phase test
nation codes and included fragmentation
program — Integral simulation of PWR
models by means of triggered propaga-
small-break LOCAs and transients — 131 (1991) 101
tion experiments in a tin/water mixture 131 (1991) 61
Maeda, N. and G. Yagawa, Some experi-
Carlucci, L.N., see Pettigrew, M.J. 131 (1991) 81
ences and development in Japan related
Carmichael, G.D.T., The Nuclear Electric
to nondestructive examination and frac-
aseismic piping research programme 131 (1991) 113
ture mechanics in structural integrity as-
Cho, S.-H., see Burger, M. 131 (1991) 61
sessment of nuclear power plant compo-
Coquerelle, M., see Walker, C.T. 131(1991) 1 nents 131 (1991) 329
Cowfer, C.D., Basis /background for ASME
Malmberg, B., Swedish approach and experi-
Code Section XI proposed Appendix
ence with inspections of austenitic com-
VIII: Ultrasonic examination perfor-
ponents in the primary circuit of BWR’s 131 (1991) 307
mance demonstration 131 (1991) 313
Manzel, R., see Walker, C.T. 131 (1991) 1
McDonald, N.R., D.H. Njo and R.W.
diMarzo, M., see Almenas, K. 131 (1991) 241 Nichols, An overview of the CSNI-PWG3
Dombret, P., Methodology for the ultrasonic Workshop on the complementary roles of
testing of austenitic stainless steel 131 (1991) 279 fracture mechanics and NDE in safety
assessments of components 131 (1991) 299
Filss, P., Fissile material detection by active Miller, A.G., A UK regulatory view of frac-
neutron interrogation with radioactive ture mechanics 131 (1991) 139
neutron sources 131 (1991) 271 Minato, A. and S. Murata, Two-dimensional
Fisher, N.J., see Pettigrew, M.J. 131 (1991) 81 analysis of discharge flow of high-pres-
Frohlich, G., Propagation of fuel—coolant in- sure saturated water from orifices 131 (1991) 25
teractions in multi-jet experiments with Miyoshi, S., Research and development of
molten tin 131 (1991) 209 ISI techniques in Japan 131 (1991) 319
Mizuno, M., see Murakami, S. 131 (1991) 147
Gobel, A., Safety aspects of the 200 MW,, Mo, Y.L., see Jost, $.D. 131 (1991) 263
Siemens Nuclear District Heating Plant, Miller, K., see Burger, M. 131 (1991) 61
348 Author Index to Volume 31
Murakami, S., M. Mizuno and T. Okamoto, Schatz, A., see Burger, M. 131 (1991) 61
Mechanical modeling of creep, swelling Schins, H., see Burger, M. 131 (1991) 61
and damage under irradiation for poly- Seshadri, B.S., Measurement of activity dis-
crystalline metals 131 (1991) 147 tributions of (D-T) neutrons in concrete 131 (1991° 187
Murata, S., see Minato, A. 131 (1991) 25 Shankar, R., see Bridgeman, J. 131 (i991) 285
Nariai, H., see Aya, I. 131 (1991) 17
Nichols, R.W., see McDonald, N.R. 131 (1991) 299 Tasaka, K., see Kukita, Y. 131 (1991) 101
Njo, D.H., see McDonald, N.R. 131 (1991) 299 Tavoularis, S., see Ouma, B.H. 131 (1991) 193
Taylor, C.E., see Pettigrew, M.J. 131 (1991) 81
Okamoto, A., see Yoshida, K. 131 (1991) 337
Okamoto, T., see Murakami, S. 131 (1991) 147
Walker, C.T., M. Coquerelle, W. Goll and
Ouma, B.H. and S. Tavoularis, Flow mea-
R. Manzel, Irradiation behaviour of
surements in rod bundle subchannels with
MOX fuel: Results of an EPMA investi-
varying rod—wall proximity 131 (1991) 193
gation 131 (1991) 1
Wu, C.C., see Almenas, K. 131 (19912)4 1
Parks, M.B., Leakage behavior of inflatable
seals subject to severe accident condi-
tions 131 (1991) 175
Yagawa, G., see Maeda, N. 131 (1991) 329
Pettigrew, M.J., L.N. Carlucci, C.E. Taylor
Yoshida, K., S. Kataoka and A. Okamoto,
and N.J. Fisher, Flow-induced vibration
Plant service continuance approach
and related technologies in nuclear com-
through periodical examination 131 (1991) 337
ponents 131 (1991) 81
Yuan, H. and W. Brocks, On the J-integral
Putney, J.M., Development of a new
concept for elastic-plastic crack extension 131 (1991) 157
bubbly-slug interfacial friction model for
Yucel, N., see Altac, Z. 131 (1991) 71
RELAPS 131 (1991) 223
Ragulskis, L., see Almenas, K. 131 (1991) 241 Zeyen, R., see Birger, M. 131 (1991) 61
349
Nuclear Engineering and Design 131 (1991) 349-350
North-Holland
Subject Index to Volume 131
Thermal and fluid design Flow measurements in rod bundle subchan-
nels with varying rod—wall proximity,
B.H. Ouma and S. Tavoularis 131 (1991) 193
Two-dimensional analysis of discharge flow
Propagation of fuel—coolant interactions in
of high-pressure saturated water from
multi-jet experiments with molten tin, G.
orifices, A. Minato and S. Murata 131 (1991) 25
Frohlich 131 (1991) 209
Reliability assessment of emergency exhaust
system in a pool-type research reactor,
Engineering mechanics
S.A. Khan 131 (1991) 37
Examination of thermal detonation codes
The Nuclear Electric aseismic piping re-
and included fragmentation models by
search programme, G.D.T. Carmichael 131 (19911)1 3
means of triggered propagation experi-
A UK regulatory view of fracture mechanics,
ments in a tin/water mixture, M. Burger,
A.G. Miller 131 (1991) 139
K. Miller, M. Buck, S.-H. Cho, A. Schatz,
Mechanical modeling of creep, swelling and
H. Schins, R. Zeyen and H. Hohmann 131 (1991) 61
damage under irradiation for polycrys-
An investigation for usage of graphite pow-
talline metals, S$. Murakami, M. Mizuno
der-helium suspension as reactor coolant
and T. Okamoto 131 (1991) 147
in a HTGR, Z. Altac and N. Yucel 131 (1991) 71
On the J-integral concept for elastic-plastic
Summary of ROSA-IV LSTF first-phase test
crack extension, H. Yuan and W. Brocks 131 (1991) 157
program — Integral simulation of PWR
An algorithm for seismic analysis of low-rise
small-break LOCAs and transients —, Y.
structural walls, $.D. Jost and Y.L. Mo 131 (1991) 263
Kukita, Y. Anoda and K. Tasaka 131 (1991) 101
An overview of the CSNI-PWG3 Workshop
Development of a new bubbly-slug interfa-
on the complementary roles of fracture
cial friction model for RELAPS, J.M.
mechanics and NDE in safety assess-
Putney 131 (1991) 223
ments of components, N.R. McDonald,
An unstable, condensation controlled two-
D.H. Njo and R.W. Nichols 131 (19912)9 9
phase natural circulation mode, K. Alme-
nas, C.C. Wu, L. Ragulskis and M. di-
Materials properties
Marzo 131 (1991) 241
Irradiation behaviour of MOX fuel: Results
of an EPMA investigation, C.T. Walker,
Heat conduction and transfer
M. Coquerelle, W. Goll and R. Manzel 131 (1991) 1
Mechanical modeling of creep, swelling and
Evaluation of heat-transfer coefficient at di- damage under irradiation for polycrys-
rect-contact condensation of cold water talline metals, S. Murakami, M. Mizuno
and steam, I. Aya and H. Nariai 131 (1991) 17 and T. Okamoto 131 (1991) 147
Propagation of fuel—coolant interactions in
multi-jet experiments with molten tin, G. Mechanical design, component fabrication and testing
Frohlich 131 (1991) 209
The Nuclear Electric aseismic piping re-
search programme, G.D.T. Carmichael 131 (1991) 113
Fluid dynamics
Methodology for the ultrasonic testing of
austenitic stainless steel, P. Dombret 131 (1991) 279
Flow-induced vibration and related tech- Erosion /corrosion data handling for reliable
nologies in nuclear components , M.J. NDE, J. Bridgeman and R. Shankar 131 (1991) 285
Pettigrew, L.N. Carlucci, C.E. Taylor and An overview of the CSNI-PWG3 Workshop
N.J. Fisher 131 (1991) 81 on the complementary roles of fracture
350
mechanics and NDE in safety assess- Isotope engineering
ments of components, N.R. McDonald,
D.H. Njo and R.W. Nichols 131 (1991) 299 Fissile material detection by active neutron
Swedish approach and experience with in- interrogation with radioactive neutron
spections of austenitic components in the sources, P. Filss 131 (1991) 271
primary circuit of BWR’s, B. Malmberg 131 (1991) 307
Core physics and fuel design
Basis /background for ASME Code Section
XI proposed Appendix VIII: Ultrasonic
Irradiation behaviour of MOX fuel: Results
examination performance demonstration,
of an EPMA investigation, C.T. Walker,
C.D. Cowfer 131 (1991) 313
M. Coquerelle, W. Goll and R. Manzel 131 (1991) 1
Research and development of ISI techniques
in Japan, S. Miyoshi 131 (19913)1 9 Nuclear safety
Plant service continuance approach through
periodical examination, K. Yoshida, S. Reliability assessment of emergency exhaust
Kataoka and A. Okamoto 131 (1991) 337 system in a pool-type research reactor,
Some experiences and development in Japan S.A. Khan 131 (1991) 37
related to nondestructive examination Summary of ROSA-IV LSTF first-phase test
and fracture mechanics in structural in- program — Integral simulation of PWR
tegrity assessment of nuclear power plant small-break LOCAs and transients -, Y.
components, N. Maeda and G. Yagawa 131 (1991) 329 Kukita, Y. Anoda and K. Tasaka 131 (1991) 101
The Nuclear Electric aseismic piping re-
Reactor concepts and systems analysis search programme, G.D.T. Carmichael 131 (1991) 113
Safety aspects of the 200 MW, Siemens
Safety aspects of the 200 MW,, Siemens Nuclear District Heating Plant, including
Nuclear District Heating Plant, including accident management measures, A.
accident management measures, A. Gobel 131 (1991) 129
Gobel 131 (1991) 129 A UK regulatory view of fracture mechanics,
A.G. Miller 131 (1991) 139
Safeguard engineering Leakage behavior of inflatable seals subject
to severe accident conditions, M.B. Parks 131 (1991) 175
Leakage behavior of inflatable seals subject An unstable, condensation controlled two-
to severe accident conditions, M.B. Parks 131 (1991) 175 phase natural circulation mode, K. Alme-
nas, C.C. Wu, L. Ragulskis and M. di-
Radiation shielding Marzo 131 (1991) 241
Overview of containment venting as an acci-
Measurement of activity distributions of (D- dent mitigation strategy in US light water
T) neutrons in concrete, B.S. Seshadri 131 (1991) 187 reactors, D.L. Kelly 131 (1991) 253