Published 2001 | Version v1
Book

Molten salts as possible fuel fluids for TRU fuelled systems: ISTC no. 1606 approach

  • 1. RRC-Kurchatov Institute, Moscow (Russian Federation)
  • 2. VNIITF, Snezinsk (Russian Federation)

Description

The principle attraction of the molten salt reactor (MSR) technology is the use of fuel/fertile material flexibility (easy of fuel preparation and processing) for gaining additional profits as compared with solid materials. This approach presents important departures from traditional philosophy, applied in current nuclear power plants, and to some extent contradicts the straightforward interpretation of the defence-in-depth principal. Nevertheless we understand there may be potential to use MSR technology to support back end fuel cycle technologies in future commercial environment. The paper aims at reviewing results of the work performed in Russia, relevant to the problems of MSR technology development. Also this contribution aims at evaluation of remaining uncertainties for molten salt burner concept implementation. Fuel properties and behaviour, container materials, and clean-up of fuels with emphasis on experiments will be of priority. Recommendations are made regarding the types of experimental studies needed on a way to implement molten salt technology to the back-end of the fuel cycle. To better understand the potential and limitations of the molten salts as a fuel for reactor of incinerator type, Russian Institutes have submitted to the ISTC the Task no. 1606 Experimental Study of Molten Salt Technology for Safe and Low Waste Treatment of Plutonium and Minor Actinides in Accelerator Driven and Critical Systems. The project goals, technical approach and expected specific results are discussed. (author)

Part of:
Actinide and fission product partitioning and transmutation

Additional details

Publishing Information

Publisher
Organisation for Economic Co-Operation and Development Nuclear Energy Agency
Imprint Place
Paris (France)
ISBN
92-64-18466-X
Imprint Title
Actinide and fission product partitioning and transmutation
Imprint Pagination
958 p.
Journal Page Range
p. 841-851

Conference

Title
6. information exchange meeting
Dates
11-13 Dec 2000
Place
Madrid (Spain)

INIS

Optional Information

Notes
13 refs.