Journal of Nuclear Materials 1992: Vol 188 Table of Contents

2 Pages·1992·0.52 MB·English

Contents
NR ss 6d cde a a d-dh cn a ES 8 en a Transient fuel behavior of preirradiated PWR fuels
under reactivity initiated accident conditions, T.
eee ene ee ees
Fujishiro, K. Yanagisawa, K. Ishijima and K. Shiba 162
Section I. Fuel Fabrication and Performance UO, fuel behavior under RIA type tests, G. Negut and
Sn Pe ic 0.0 ks Cpe eae a be eae 168
Irradiation behavior of metallic fast reactor fuels, R.G. On the kinetics of UO, interaction with molten
Pahl, D.L. Porter, D.C. Crawford and L.C. Walters . Zircaloy at high temperatures, M.S. Veshchunov
MOX fuel development: yesterday, today and tomor- GU a PE 6.8.6.5 06 6 se eee 177
row, H. Bairiot and P. Deramaix 10
ecpéeecenene £24 ¢.6-2 @
Development and characteristics of the rim region in
high burnup UO, fuel pellets, M.E. Cunningham, Section III. Basic Properties of Nuclear Materials
M.D. Freshley and D.D. Lanning 19
Preparation of uranium nitride in the form of micro-
spheres, G. Ledergerber, Z. Kopajtic, F. Ingold and Neutron irradiation effects in boron carbides: Evolu-
8 ee ee ee ee ae ee 28 tion of microstructure and thermal properties, K.
Mechanism and kinetics of the uranium—plutonium Froment, D. Gosset, M. Guéry, B. Kryger and C.
mononitride synthesis, P. Bardelle and D. Warin ee ee ee ee 185
Irradiation of a 19 pin subassembly with mixed carbide On the theory of high temperature transition in fluo-
fuel in KNK II, D. Geithoff, G. Miihling and K. rite-type oxides, M.S. Veshchunov 189
$464.9 2,6%89 45 0
Thermal conductivity of (U, PuJO,_, mixed oxide fuel,
Richter
2.266.586.8538 SD 2 8.40.6 DEA CH OE HOEH EEA ATS
Fission product behaviour in Phenix fuel pins at high Fs EE dg wa we oes be Ko oe SE 194
burnup, M. Tourasse, M. Boidron and B. Pasquet . . Thermal conductivity of SIMFUEL, P.G. Lucuta, Hj.
Fission product behaviour in fast breeder fuel pins, O. Matzke, R.A. Verrall and H.A. Tasman 198
Gotzmann High temperature heat capacities and electrical con-
Microstructural change and its influence on fission gas ductivities of UO, doped with yttrium and simu-
release in high burnup UO, fuel, K. Une, K. Nogita, lated fission products, 7. Matsui, Y. Arita and K.
S. Kashibe and M. Imamura ...........00045. 65 eeee re ae a ee 205
Concerning the microstructure changes that occur at Defect structure and oxygen diffusion in UO,,°5, J.P.
the surface of UO, pellets on irradiation to high Goff, B. Fak, W. Hayes and M.T. Hutchings ...... 210
burnup, C.T. Walker, T. Kameyama, S. Kitajima and A comparison of the behaviour of fission gases in
M. Kinoshita 73 UO,,, and a-U,0,_,, RGJ. Ball and RW.
£20.00 428968 6.686 68.456 98404 686684 62.8
Microstructural analysis of LWR spent fuels at high Grimes 2-8: 8S SCA 6.4 6.0 2 82 8.246.848 64 6 O92 4°42 OES 216
burnup, L.E. Thomas, C.E. Beyer and L.A. Charlot 80 Effect of temperature on bubble precipitation in ura-
Transmission electron microscopy study of fission nium dioxide implanted with krypton and xenon
product behaviour in high burnup UO,, /.L.F. Ray, I PS ye rere eS eT Tee CT er 222
See Pee GE es CE hsb wo oie s twa wn Beda 90 Investigation of nuclear mixed oxide fuel—gas interac-
Fuel performance under normal PWR conditions: A tion by a solid electrolyte based coulometric tech-
review of relevant experimental results and models, nique, K. Teske, C. Nebelung, H. Ullman, LI. Kap-
M. Charles and C. Lemaignan 96 shukov, L.V. Sudakov and A.S. Bevz ........... 226
Nonideality of the solid solution in (U, PuJO, nuclear
Fuel rod and core materials investigations related to
LWR extended burnup operation, E. Kolstad and Se ic K Waw sou dade cba ds ewan sé’ 232
C. Vitanza 104 Vaporization behavior of uranium—plutonium mixed
nitride, Y. Suzuki, A. Maeda, Y. Arai and T. Ohmi-
Section II. Reactor Safety ee nice bh ceed a ee 6 4k eee ek 239
The fate of nitrogen upon reprocessing of nitride fuels,
The Phebus fission product project, P. von der Hardt N. Hadibi-Olschewski, J.-P. Glatz, H. Bokelund and
and A. Tattegrain 115 M.J.-F. Leroy 244
Seeaesv ase seen e &€ 6 6-4 6 O18 6 €. 4 @ 6 O82 S 2 6 Fee 2.370 2.4 4626 2 e646 OSS 8S
Information on the evolution of severe LWR fuel ele- Stability and structure of the 8 phase of the U-Zr
ment damage obtained in the CORA program, G. alloys, M. Akabori, A. Itoh, T. Ogawa, F. Kobayashi
Schanz, S. Hagen, P. Hofmann, G. Schumacher and EE 8 bok 4 Oe ae 8 249
i EE <a @ 3-6-n-050 460-504 OES ORE AES o 131 Study of the oxidation of a stainless steel under BWR
Fuel behaviour under severe accident conditions: In- conditions by advanced analytical techniques, C.
terpretation of PTE results from the CABRI test Degueldre, J.C. Dran and E. Schenker .......... 255
programme, H. Steiner 146 Modelling of inert gas bubble behaviour during anneal-
ch See 8.2 SO e C.O' SOS. 2 4 2 4'O
Failure behavior of plutonium-uranium mixed oxide ing of irradiated molybdenum, V.F. Chkuaseli . 258
fuel under reactivity-initiated accident condition, T. Mass and gamma spectrometric measurements of fis-
Abe, N. Nakae, K. Kodato, M. Matsumoto and T. sion products released from overheated, fresh irra-
diated, uranium dioxide, R.H.J. Tanke
See Prev eec OP SCRE A CAA CEE ED OS OE SES BB 2-6. 6-8 6.0 64 6.6
Contents
Structural analysis of oxide scales grown on zirconium Mechanistic model of fission gas behavior in metallic
alloys in autoclaves and in a PWR, H. Blank, G. fuel, Y. Tsuboi, T. Ogata, M. Kinoshita and H. Saito
Bart and H. Thiele Simplified model for the analysis on the duct wall
Carbon activity measurements in boron carbides using deflection due to in-reactor creep in LMFBR fuel
a solid state potentiometric cell, K. Froment, C. assemblies, S. Komoda, N. Nakae and M. Mat-
Chatillon, J. Fouletier and M. Fouletier sumoto
Ion implantation studies of UO, and UN, Hj. Matzke Modelling of (U, Gd)O, fuel behaviour in boiling wa-
and A. Turos ter reactors, A.R. Massih, S. Persson and Z. Weiss
Development of the thermal behavior analysis code
Section IV. Modelling of Fuel Performance DIRAD and the fuel design procedure for LMFBR,
N. Nakae, K. Tanaka, H. Nakajima and M. Mat-
TRANSURANUS: a fuel rod analysis code ready for sumoto
use, K. Lassmann
GERMINAL - A computer code for predicting fuel
pin behaviour, J.C. Melis, L. Roche, J.P. Piron and J.
Truffert
Modelling fission gas behaviour in mixed oxide fuel
under normal and off-normal conditions in fast
reactors, L. Vath