Inherent Safety of Fuels for Accelerator-Driven Systems
- 1 September 2005
- journal article
- research article
- Published by Informa UK Limited in Nuclear Technology
- Vol. 151 (3), 314-333
- https://doi.org/10.13182/nt05-a3654
Abstract
Transient safety characteristics of accelerator-driven systems using advanced minor actinide fuels have been investigated. Results for a molybdenum-based Ceramic-Metal (CerMet) fuel, a magnesia-based Ceramic-Ceramic fuel, and a zirconium-nitride–based fuel are reported. The focus is on the inherent safety aspects of core design. Accident analyses are carried out for the response to unprotected loss-of-flow and accelerator beam-overpower transients and coolant voiding scenarios. An attempt is made to establish basic design limits for the fuel and cladding. Maximum temperatures during transients are determined and compared with design limits. Reactivity effects associated with coolant void, fuel and structural expansion, and cladding relocation are investigated. Design studies encompass variations in lattice pitch and pin diameter. Critical mass studies are performed. The studies indicate favorable inherent safety features of the CerMet fuel. Major consideration is given to the potential threat of coolant voiding in accelerator-driven design proposals. Results for a transient test case study of a postulated steam generator tube rupture event leading to extensive coolant voiding are presented. The study underlines the importance of having a low coolant void reactivity value in a lead-bismuth system despite the high boiling temperature of the coolant. It was found that the power rise following a voiding transient increases dramatically near the critical state. The studies suggest that a reactivity margin of a few dollars in the voided state is sufficient to permit significant reactivity insertions.Keywords
This publication has 18 references indexed in Scilit:
- Investigation upon the dynamic structural response of a nuclear plant on aseismic isolating devicesNuclear Engineering and Design, 2004
- The chemistry and physics of modelling nitride fuels for transmutationJournal of Nuclear Materials, 2003
- Neutronic aspects of inert matrix fuels for application in ADSJournal of Nuclear Materials, 2003
- Fabrication of nitride fuels for transmutation of minor actinidesJournal of Nuclear Materials, 2003
- Thermo-Calc & DICTRA, computational tools for materials scienceCalphad, 2002
- Some aspects of the use of ZrN as an inert matrix for actinide fuelsJournal of Nuclear Materials, 2001
- Selection of materials as diluents for burning of plutonium fuels in nuclear reactorsJournal of Nuclear Materials, 1999
- Melting behaviour of oxide systems for heterogeneous transmutation of actinides. III. The system Am–Mg–OJournal of Nuclear Materials, 1997
- Melting behaviour of oxide systems for heterogeneous transmutation of actinides. I. The systems PuAlO and PuMgOJournal of Nuclear Materials, 1997
- Synergistic tellurium–caesium embrittlement of Type 316 stainless steelNature, 1982