Melting temperature of simulated high-burnup mixed oxide fuels for fast reactors

Citation
K. Konno et T. Hirosawa, Melting temperature of simulated high-burnup mixed oxide fuels for fast reactors, J NUC SCI T, 36(7), 1999, pp. 596-604
Citations number
21
Categorie Soggetti
Nuclear Emgineering
Journal title
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY
ISSN journal
00223131 → ACNP
Volume
36
Issue
7
Year of publication
1999
Pages
596 - 604
Database
ISI
SICI code
0022-3131(199907)36:7<596:MTOSHM>2.0.ZU;2-#
Abstract
The melting (solidus) temperatures were measured for fuel simulating burnup s of 50, 90, 130, 170, 210 and 250 GWd/t (SIMFUEL) which were added non-rad ioactive soluble fission products (FPs) to unirradiated fast reactor MOX fu el. The melting temperatures for fuels of 250 GWd/t which were blended non- radioactive soluble FPs and irradiated fuels of 110.6 and 119.0 GWd/t were also compared to the SIMFUEL of 250 GWd/t. The melting temperature decrease of the SIMFUEL tended to saturate with increasing burnup and the melting t emperatures appeared virtually constant above 170 GWd/t. An equation for me lting temperature was obtained from the proposed equation in the previous r eport by revising the coefficient of the fifth term: T-m = 3, 133.8 - 460X(1) - 980X(2) - 0.66X(3) + 0.0008(X-3)(2), where T-m is the expected melting temperature (K); X-1 the plutonium fracti on (Pu/(Pu+U)), X-2 the americium fraction (Am/(Pu+U+Am)), and X-3 the burn up (GWd/t). After the temperature measurement, the radial distribution of eight FP oxid e additives in SIMFUEL of 250 GWd/t was measured by X-ray microanalysis. Re lative characteristic X-ray intensities of Zr, Ce, La and Sr had the same r adial profiles, whilst they did not correspond to the X-ray intensity profi les of Nd and Y.