LMFBR subassembly response to simulated local pressure loadings
- 1. Argonne National Lab., Ill. (USA)
- 2. Stanford Research Inst., Menlo Park, Calif. (USA). Poulter Labs.
Description
The structural response of liquid metal fast breeder reactor (LMFBR) subassemblies to local accidental events is of interest in assessing the safety of such systems. Problems to be resolved include failure propagation modes from pin to pin and from subassembly to subassembly. Factors which must be considered include: (a) the geometry of the structure, (b) uncertainty of the pressure-energy source, (c) uncertainty of materials properties under reactor operating conditions, and (d) the difficulty in performing in-pile or out-of-pile experiments which would simulate the above conditions. The main effort in evaluating the subassembly response has been centered around the development of appropriate analyses based on the finite element technique. Analysis has been extended to include not only the subassembly duct structure itself, but also the fluid environment, both within subassemblies and between them. These models and codes have been devised to cover a wide range of accident loading conditions, and can treat various materials as their properties become known. The effort described here is centered mainly around an experimental effort aimed at verfying, modifying or extending the models used in treating subassembly damage propagation. To verify the finite element codes under development, a series of out-of-pile room temperature experiments has been performed on LMFBR-type subassembly ducts under various loading conditions. (Auth.)
Additional details
Identifiers
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 38
- Journal Issue
- 1
- Series
- Nucl. Eng. Des.
- Journal Page Range
- 1-14
- ISSN
- 0029-5493
Conference
- Title
- International seminar on extreme load conditions and limit analysis procedures for structural reactor safeguards and containment structures.
- Dates
- 8 Sep 1975.
- Place
- Berlin, Germany.
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 8301391
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FINITE ELEMENT METHOD; HARDNESS; LMFBR TYPE REACTORS; MATHEMATICAL MODELS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR SAFETY; RESPONSE FUNCTIONS; S CODES; SIMULATION; STAINLESS STEEL-316; STRAINS; STRESSES; THREE-DIMENSIONAL CALCULATIONS; TWO-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- ACCIDENTS; ALLOYS; BREEDER REACTORS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM STEELS; CHROMIUM-NICKEL STEELS; COMPUTER CODES; CORROSION RESISTANT ALLOYS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUNCTIONS; HEAT RESISTING ALLOYS; IRON ALLOYS; IRON BASE ALLOYS; LIQUID METAL COOLED REACTORS; MECHANICAL PROPERTIES; MOLYBDENUM ALLOYS; NICKEL ALLOYS; NUMERICAL SOLUTION; REACTORS; SAFETY; STAINLESS STEELS; STEELS; TRANSITION ELEMENT ALLOYS
Optional Information
- Notes
- Updated automatically by Metadata and Full-Text Enrichment Agent