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Van Rooyen, I. J.*; Ivan, L.*; Messner, M.*; Edwards, L.*; Abonneau, E.*; Kamiji, Yu; Lowe, S.*; Nilsson, K.-F.*; Okajima, Satoshi; Pouchon, M.*; et al.
Proceedings of 4th International Conference on Generation IV and Small Reactors (G4SR-4), p.2 - 12, 2022/10
F
tterer, M. A.*; Strydom, G.*; Sato, Hiroyuki; Li, F.*; Abonneau, E.*; Abram, T.*; Davies, M. W.*; Kim, M. H.*; Edwards, L.*; Muransky, O.*; et al.
Encyclopedia of Nuclear Energy, Vol.1, p.512 - 522, 2021/06
The HTR is a relatively simple Small Modular Reactor design featuring demonstrated robust passive and inherent safety. It responds to the needs of a very large and growing process heat market in most industrialized countries many of which pursue a stringent policy of reducing fossil fuel burn. The manuscript starts from historical developments. This article also highlights the most significant recent achievements of this technology internationally and explains its potential value in a modern energy economy beyond pure electricity generation. The article concludes with an outlook on work towards building demonstration plants, which are required to de-risk private investments and to incentivize deployment.
Ftterer, M. A.*; Li, F.*; Gougar, H.*; Edwards, L.*; Pouchon, M. A.*; Kim, M. H.*; Carr
, F.*; Sato, Hiroyuki
Proceedings of 9th International Topical Meeting on High Temperature Reactor Technology (HTR 2018) (USB Flash Drive), 12 Pages, 2018/10
This paper provides an update on the international effort in the development of the VHTR system pursued through international collaboration between 8 countries in the GIF and an outlook on future R&D. The versatility of the VHTR enables it to be designed with inherent safety characteristics and optimized for both electric and non-electric applications, in particular for cogeneration of heat and power. Recent highlights from the four currently active GIF VHTR R&D projects are provided and placed into the context of the related national programs. Based on VHTR's relatively high technology readiness level, orientations for future R&D are outlined and will contribute to further enhancing the system's market readiness level.
Pouchon, M. A.
JNC TN8520 2002-002, 29 Pages, 2002/04
JNC-TN8520-2002-002.pdf:1.07MB
A tool for analyzing ceramographic cuts of sphere beds was programmed. The parameter of interest was the neck ratio being formed during sintering. A neck investigation based on such a cross section was programmed in a way, that the cross section discs could be entered graphically, and that the necking data was extracted from this information. In a resulting graphic the neck information on the surface was overlaid and could be crosschecked with the actual visible necking data. This allowed a quality control of the extracted data but was also necessary to exclude some false solution being introduced by the principle how the data was extracted. Some test on cross sections of a Cer-Med Sphere-Bed showed good results.
Pouchon, M. A.
JNC TN8520 2002-001, 271 Pages, 2002/04
JNC-TN8520-2002-001.pdf:0.87MB
A tool for meshing sphere arrangements was programmed in order to perform finite element calculations. Sphere arrangements are investigated in frame of the feasibility study of the sphere-pac nuclear fuel. One major concern of this study is the thermal conductivity of the arrangement. Further concerns are the mechanical behavior and sintering of the fuel. The thermal conductivity of the fuel was addressed with the computer code SPACON based on a unit cell approach and a radial heat flow experiment. However, a further approach using the finite element method is desirable, in order to better understanding the thermal flow through the package and to cross check with SPACON data and with experimental data. Also the mechanical behavior of the fuel could be addressed using the finite element technique.
; ; Pouchon, M. A.
Proceedings of Actinides 2001, 0 Pages, 2001/11
In the feasibility study of a FBRcycle system,alternative nuclear fuel designs are considered. The "sphere-pac" fuel design is one option, which consists of a spherical particle bed vibro-packed into the fuel pin cladding. The advantages of this concept would be a less-powder in fuel production and a lower mechanical interaction between fuel and cladding. JNC has developed a new fuel irradiation behavi
Pouchon, M. A.;
Proceedings of Actinides 2001, 0 Pages, 2001/11
As an alternative concept,a particle arrangement(sphere-pac or vibro-pac type)is considered as fuel-form for burning actinides. The fuel material is potentially MOX or an Inert Matrix like yttria stabilized zirconia. A weak point of particle fuel is its thermal conductivity at startup.Before sintering initiates the macroscopic structure of the sphere-pac decreases the energy transport. For a partial
Pouchon, M. A.; ;
Beikoku Seramikku Gakkai Dai-103-Kai Nenji Taikai, 0 Pages, 2000/00
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