Thermal hydraulic aspects in the analysis of LMFBR disrupted-core situations
Abstract
This paper presents the thermal-hydraulic aspects of current interest in the modeling of LMFBR hypothetical core-disruptive accidents, with special emphasis on the Loss of Flow situations. The models presented have been incorporated in LEVITATE, a code for the analysis of fuel and cladding dynamics under LOF conditions, which has recently become part of the SAS4A code system. The influence of different thermal-hydraulic models on fuel motion is illustrated by a comparison between the results calculated by LEVITATE, the data from the L7-TREAT experiment and the results calculated by SLUMPY. The results calculated by LEVITATE are in fair agreement with the experimentally observed early fuel dispersal. The marginally acceptable energetic events obtained in the analysis of high void-worth LMFBR cores during Loss-of-Flow transients coupled with uncertainties about some of the thermal-hydraulic parameters motivate, among other factors, the need for the design low void-worth LMFBR cores.
- Authors:
- Publication Date:
- Research Org.:
- Argonne National Lab., IL (USA)
- OSTI Identifier:
- 6487852
- Report Number(s):
- CONF-8110112-2
ON: DE83008699
- DOE Contract Number:
- W-31-109-ENG-38
- Resource Type:
- Conference
- Resource Relation:
- Conference: Specialists' meeting on liquid metals thermal hydraulics, Cambridge, MA, USA, 5 Oct 1981
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; LMFBR TYPE REACTORS; LOSS OF FLOW; REACTOR CORE DISRUPTION; HEAT TRANSFER; HYDRAULICS; COMPUTER CALCULATIONS; HYDRODYNAMICS; REACTOR SAFETY; ACCIDENTS; BREEDER REACTORS; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FLUID MECHANICS; LIQUID METAL COOLED REACTORS; MECHANICS; REACTOR ACCIDENTS; REACTORS; SAFETY; 220900* - Nuclear Reactor Technology- Reactor Safety; 210500 - Power Reactors, Breeding
Citation Formats
Tentner, A M, and Wider, H U. Thermal hydraulic aspects in the analysis of LMFBR disrupted-core situations. United States: N. p., 1981.
Web.
Tentner, A M, & Wider, H U. Thermal hydraulic aspects in the analysis of LMFBR disrupted-core situations. United States.
Tentner, A M, and Wider, H U. 1981.
"Thermal hydraulic aspects in the analysis of LMFBR disrupted-core situations". United States. https://www.osti.gov/servlets/purl/6487852.
@article{osti_6487852,
title = {Thermal hydraulic aspects in the analysis of LMFBR disrupted-core situations},
author = {Tentner, A M and Wider, H U},
abstractNote = {This paper presents the thermal-hydraulic aspects of current interest in the modeling of LMFBR hypothetical core-disruptive accidents, with special emphasis on the Loss of Flow situations. The models presented have been incorporated in LEVITATE, a code for the analysis of fuel and cladding dynamics under LOF conditions, which has recently become part of the SAS4A code system. The influence of different thermal-hydraulic models on fuel motion is illustrated by a comparison between the results calculated by LEVITATE, the data from the L7-TREAT experiment and the results calculated by SLUMPY. The results calculated by LEVITATE are in fair agreement with the experimentally observed early fuel dispersal. The marginally acceptable energetic events obtained in the analysis of high void-worth LMFBR cores during Loss-of-Flow transients coupled with uncertainties about some of the thermal-hydraulic parameters motivate, among other factors, the need for the design low void-worth LMFBR cores.},
doi = {},
url = {https://www.osti.gov/biblio/6487852},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Jan 01 00:00:00 EST 1981},
month = {Thu Jan 01 00:00:00 EST 1981}
}