Published 1995
| Version v1
Book
Feasibility studies of a highly moderated 100% MOX fuelled PWR concept
- 1. CEA Centre d'Etudes de Cadarache, 13 - Saint-Paul-lez-Durance (France). Dept. d'Etudes des Reacteurs
- 2. CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Dept. de Mecanique et de technologie
Description
A severe loss of control means is caused by fuelling a PWR with 100% of MOX assemblies at the moderating ratio R=2. The study of a 100% MOX Highly Moderated Reactor leads to an opportunity of a good neutronic feasibility and power capacity. These studies show there is a real advantage to increase the moderating ratio in order to improve plutonium consumption, as well as minor actinides wastes. The state of the study allows to choose two assemblies, a 17 x 17 one with R=3.1 and a 19 x 19 with R=4.0. (author)
Additional details
Publishing Information
- Publisher
- Edition ANS
- Imprint Place
- Paris (France)
- Imprint Title
- Global 1995
- Imprint Pagination
- 2032 p.
- Journal Page Range
- p. 1308-1315
Conference
- Title
- International conference on evaluation of emerging nuclear fuel cycle systems
- Dates
- 11-14 Sep 1995
- Place
- Versailles (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 29066550
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FUEL PINS; MIXED OXIDE FUELS; MODERATING RATIO; NEUTRON TRANSPORT THEORY; PLUTONIUM; PWR TYPE REACTORS; REACTOR CORES
- Descriptors DEC
- ACTINIDES; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; FUELS; MATERIALS; METALS; NUCLEAR FUELS; POWER REACTORS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SOLID FUELS; THERMAL REACTORS; TRANSPORT THEORY; TRANSURANIUM ELEMENTS; WATER COOLED REACTORS; WATER MODERATED REACTORS