Safety assessment of two advanced ferritic steel molten salt blanket design concepts
Creators
- 1. INEEL Fusion Safety Program, P.O. Box 1625, Idaho Falls, ID 83415-3860 (United States)
- 2. University of Wisconsin, Madison, WI (United States)
- 3. General Atomics, San Diego, CA (United States)
- 4. Sandia National Laboratories, P.O. Box 5800, Albuquerque, NM (United States)
- 5. Fusion Nuclear Technology Consulting Fliederweg 3, 76351 Linkenheim (Germany)
- 6. University of California, San Diego, CA (United States)
Description
In this article, we explore some of the safety issues associated with two advanced ferritic steel (AFS) molten salt blanket designs from the Advanced Power Extraction (APEX) design study [M.A. Abdou, The APEX Team, On the exploration of innovative concepts for fusion chamber technology, Fus. Eng. Des. 54 (2000) 181]. In particular, we examine radiological inventories, decay heat, waste disposal ratings, and toxic chemical inventories of these design concepts. In addition, we predict the thermal response of these blanket designs during accident conditions, and the mobilization of the radiological inventories and site boundary dose from the release of this mobilized material during a worst-case confinement-boundary-bypass accident. The molten salts being proposed for these blanket concepts are Flibe and Flinabe, and the structural material is a nano-composite strengthened ferritic steel alloy called 12YWT. The estimated dose at the site boundary is less than the no-evacuation limit of 10 mSv for a ground level release during conservative weather conditions if plant isolation occurs within 5 days
Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2004.07.010;
- PII
- S0920-3796(04)00119-X;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 72
- Journal Issue
- 1-3
- Journal Page Range
- p. 277-306
- ISSN
- 0920-3796
- CODEN
- FEDEEE
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 36074663
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- BYPASSES; DESIGN; DOSES; FERRITIC STEELS; FIRST WALL; FLIBE; GROUND LEVEL; INVENTORIES; LOSS OF COOLANT; RISK ASSESSMENT; SAFETY; THERMONUCLEAR REACTORS; WASTE DISPOSAL
- Descriptors DEC
- ACCIDENTS; ALLOYS; CARBON ADDITIONS; IRON ALLOYS; IRON BASE ALLOYS; LEVELS; MANAGEMENT; MOLTEN SALTS; REACTOR ACCIDENTS; SALTS; STEELS; THERMONUCLEAR REACTOR WALLS; TRANSITION ELEMENT ALLOYS; WASTE MANAGEMENT
Optional Information
- Copyright
- Copyright (c) 2004 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.