scholarly journals Scoping study of flowpath of simulated fission products during secondary burning of crushed HTGR fuel in a quartz fluidized-bed burner

1976 ◽  
Author(s):  
J Rindfleisch ◽  
V Barnes
Author(s):  
R. J. Lauf

Fuel particles for the High-Temperature Gas-Cooled Reactor (HTGR) contain a layer of pyrolytic silicon carbide to act as a miniature pressure vessel and primary fission product barrier. Optimization of the SiC with respect to fuel performance involves four areas of study: (a) characterization of as-deposited SiC coatings; (b) thermodynamics and kinetics of chemical reactions between SiC and fission products; (c) irradiation behavior of SiC in the absence of fission products; and (d) combined effects of irradiation and fission products. This paper reports the behavior of SiC deposited on inert microspheres and irradiated to fast neutron fluences typical of HTGR fuel at end-of-life.


Author(s):  
Joan Fontanet ◽  
Luis E. Herranz ◽  
Alastair Ramlakan ◽  
Lolan Naicker

A scoping study on a confinement approach to a PBMR type plant was performed to quantify its performance in terms of retention and thermal-hydraulics in case of a postulated breach in the Helium Pressure Boundary. This paper introduces a simulation strategy for accident analyses of a PBMR confinement. Based on two accident sequences characterized by Helium Pressure Boundary breaches, a small (AOO) and a large (DBA) break, the estimates from the ASTEC and CONTAIN codes are presented and compared to check their capabilities and consistency. The results obtained indicate that both codes predict very similar thermal-hydraulic responses of the confinement both in magnitude and timing. As for the aerosol behaviour, both codes predict that most of inventory coming into the confinement is eventually depleted on the walls and only about 1% of the aerosol dust is released to environment. The cross-comparison of codes states that largest differences are in the inter-compartmental flows and the in-compartment gas composition. Concerning the capabilities of the codes, CONTAIN has shown to be more robust in dealing with the injection of large aerosol mass flow and with a very small injection of fission products. ASTEC however has an ad-hoc model for aerosol retention in filters.


1993 ◽  
Vol 202 (1-2) ◽  
pp. 47-53 ◽  
Author(s):  
Kazuo Minato ◽  
Toru Ogawa ◽  
Kousaku Fukuda ◽  
Hajime Sekino ◽  
Hideyuki Miyanishi ◽  
...  

1985 ◽  
Vol 136 (2-3) ◽  
pp. 207-217 ◽  
Author(s):  
K. Hayashi ◽  
T. Kikuchi ◽  
F. Kobayashi ◽  
K. Minato ◽  
K. Fukuda ◽  
...  

Atomic Energy ◽  
1992 ◽  
Vol 73 (2) ◽  
pp. 612-617
Author(s):  
A. I. Deryugin ◽  
A. S. Chernikov ◽  
B. P. Kolesnikov ◽  
K. N. Koshcheev ◽  
A. D. Kurepin

1977 ◽  
Author(s):  
R.P. Wichner ◽  
F.F. Dyer ◽  
W.J. Martin ◽  
L.C. Bate

1977 ◽  
Author(s):  
R.P. Wichner ◽  
F.F. Dyer ◽  
W.J. Martin ◽  
L.L. Fairchild

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