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Title: SAS/FCI: a fuel-coolant interaction model for LMFBR whole-core accident analysis

Abstract

From national topical meeting on mathematical models and computational techniques for analysis of nuclear systems; Ann Arbor, Michigan, USA (8 Apr 1973). In mathematical models and computational techniques for analysis of nuclear systems. A molten fuel-coolant interaction model is described for the analysis of LMFBR hypothetical core disruptive accidents. The concept of a point model is employed, but in addition to a uniform interaction zone in the coolant channel, a uniform fuel-pin cavity pressurized by fission gas is modeled for the ejection of fuel and fission gas from the fuel pin to the interaction zone. Both the fuel- pin cavity model and the interaction zone model permit timedependent masses for their respective components. Pressurization of the interaction zone is relieved by motion of the inertial liquid sodium slugs which constrain the interaction zone volume, by heat transfer from the interaction zone sodium to the subassembly structure and fuel-pin cladding, and by addition of subcooled sodium to the interaction zone. Reactivity feedhacks due to sodium voiding and fuel loss from the fuel pin are calculated by assuming uniform density decreases, whereas that due to fuel motion in the coolant channel is calculated by assuming uniform dilation of the interaction zone. 8more » references. (auth)« less

Authors:
; ; ; ;
Publication Date:
Research Org.:
Argonne National Lab., IL; American Nuclear Society. Michigan Section
OSTI Identifier:
4373943
Report Number(s):
CONF-730414-P1
NSA Number:
NSA-29-007066
Resource Type:
Conference
Resource Relation:
Conference: National topical meeting on mathematical models and computational techniques for analysis of nuclear systems, Ann Arbor, Michigan, USA, 8 Apr 1973; Other Information: Orig. Receipt Date: 30-JUN-74; Related Information: Mathematical models and computational techniques for analysis of nuclear systems
Country of Publication:
Country unknown/Code not available
Language:
English
Subject:
N77900* -Reactors-Reactor Safety & Environmental Aspects; N77500 -Reactors-Power Reactors, Breeding; *FBR TYPE REACTORS; *LMFBR TYPE REACTORS- REACTOR CORE DISRUPTION; LIQUID FLOW; MATHEMATICAL MODELS; REACTOR SAFETY; THERMODYNAMICS LMFBR TYPE REACTORS

Citation Formats

Smith, L L, Travis, J R, Stevenson, M G, Dunn, F E, and Fischer, G J. SAS/FCI: a fuel-coolant interaction model for LMFBR whole-core accident analysis. Country unknown/Code not available: N. p., 1973. Web.
Smith, L L, Travis, J R, Stevenson, M G, Dunn, F E, & Fischer, G J. SAS/FCI: a fuel-coolant interaction model for LMFBR whole-core accident analysis. Country unknown/Code not available.
Smith, L L, Travis, J R, Stevenson, M G, Dunn, F E, and Fischer, G J. 1973. "SAS/FCI: a fuel-coolant interaction model for LMFBR whole-core accident analysis". Country unknown/Code not available.
@article{osti_4373943,
title = {SAS/FCI: a fuel-coolant interaction model for LMFBR whole-core accident analysis},
author = {Smith, L L and Travis, J R and Stevenson, M G and Dunn, F E and Fischer, G J},
abstractNote = {From national topical meeting on mathematical models and computational techniques for analysis of nuclear systems; Ann Arbor, Michigan, USA (8 Apr 1973). In mathematical models and computational techniques for analysis of nuclear systems. A molten fuel-coolant interaction model is described for the analysis of LMFBR hypothetical core disruptive accidents. The concept of a point model is employed, but in addition to a uniform interaction zone in the coolant channel, a uniform fuel-pin cavity pressurized by fission gas is modeled for the ejection of fuel and fission gas from the fuel pin to the interaction zone. Both the fuel- pin cavity model and the interaction zone model permit timedependent masses for their respective components. Pressurization of the interaction zone is relieved by motion of the inertial liquid sodium slugs which constrain the interaction zone volume, by heat transfer from the interaction zone sodium to the subassembly structure and fuel-pin cladding, and by addition of subcooled sodium to the interaction zone. Reactivity feedhacks due to sodium voiding and fuel loss from the fuel pin are calculated by assuming uniform density decreases, whereas that due to fuel motion in the coolant channel is calculated by assuming uniform dilation of the interaction zone. 8 references. (auth)},
doi = {},
url = {https://www.osti.gov/biblio/4373943}, journal = {},
number = ,
volume = ,
place = {Country unknown/Code not available},
year = {Mon Jan 01 00:00:00 EST 1973},
month = {Mon Jan 01 00:00:00 EST 1973}
}

Conference:
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