Generation-IV nuclear power (Record no. 169280)
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| 000 -LEADER | |
|---|---|
| fixed length control field | 01997nab a2200193 4500 |
| 008 - CÓDIGOS DE INFORMACIÓN DE LONGITUD FIJA - INFORMACIÓN GENERAL | |
| Campo de control de longitud fija | 260224s2008 xxu |
| 245 00 - TITULO | |
| Título | Generation-IV nuclear power |
| Subtítulo | A review of the state of the science |
| 260 ## - PUBLICACION, DISTRIBUCION, ETC | |
| Lugar de publicación, distribución, etc. | |
| Nombre de publicador, distribuidor, etc. | |
| Fecha de publicación, distribución, etc. | dic. 2008 |
| 270 ## - FECHA DE CARGA | |
| Fecha de carga | 20/03/2009 ; 20/03/2009 |
| 300 ## - DESCRIPCION FISICA | |
| Otra extensión | 7 p. ; 4323-4330 |
| 520 ## - RESUMEN, ETC | |
| Resumen | Transcripción del resúmen publicado por el autor: The Generation-IV consortium seeks to develop a new generation of nuclear energy systems for commercial deployment by 2020–2030. These systems include both the reactors and their fuel-cycle facilities. The aim is to provide significant improvements in economics, safety, sustainability, and proliferation resistance. The systems selected for development are the very high-temperature gas-cooled reactor (VHTR), the sodium-cooled fast reactor (SFR), the gas-cooled fast reactor (GFR), the lead-cooled fast reactor (LFR), the molten salt reactor (MSR) and the super-critical water-cooled reactor (SCWR). UK organisations plan to contribute to the first three of these systems because of its existing capabilities and experience with gas-cooled systems, graphite cores, and SFRs. The science base for the VHTR and SFR systems is reasonably established, although there are gaps. For the VHTR, these include the performance of graphite at high neutron doses, and the performance of the fuel. For the SFR, the behaviour of fuels containing minor actinides, and processes for their recycling and refabrication into new fuel, must be established. The GFR presents many technical challenges, because it would need fuel and structural materials capable of withstanding extremes of fast neutron flux and high temperatures. Adequate heat removal from the core under fault conditions is likely to determine its feasibility. |
| 581 ## - ESTADO DE COLECCIÓN | |
| Estado de colección | 12 |
| 773 0# - CORRECCIÓN | |
| Título | Energy Policy |
| Partes relacionadas | 36 |
| 942 ## - DESC. DE MATERIAL | |
| Tipo de item KOHA | Artículo de Revista |
| 100 1# - RESPONSABLE PERSONAL | |
| Apellido, Nombre | Abram, Tim |
| 9 (RLIN) | 40555 |
| 100 1# - RESPONSABLE PERSONAL | |
| Apellido, Nombre | Ion, Sue |
| 9 (RLIN) | 40556 |
| Biblioteca propietaria | Biblioteca actual | Fecha de adquisición | Inventario | Total de préstamos | Inventario | Fecha de carga | Tipo de item KOHA |
|---|---|---|---|---|---|---|---|
| Biblioteca Alejandro Angel Bulgheroni | Biblioteca Alejandro Angel Bulgheroni | 05/03/2026 | 200044078 | 200044078 | 05/03/2026 | Artículo de Revista |
