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SIMMER as a safety analysis tool

Description: SIMMER has been used for numerous applications in fast reactor safety, encompassing both accident and experiment analysis. Recent analyses of transition-phase behavior in potential core disruptive accidents have integrated SIMMER testing with the accident analysis. Results of both the accident analysis and the verification effort are presented as a comprehensive safety analysis program.
Date: January 1, 1982
Creator: Smith, L. L.; Bell, C. R.; Bohl, W. R.; Bott, T. F.; Dearing, J. F. & Luck, L. B.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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LMFBR system-wide transient analysis: the state of the art and US validation needs

Description: This paper summarizes the computational capabilities in the area of liquid metal fast breeder reactor (LMFBR) system-wide transient analysis in the United States, identifies various numerical and physical approximations, the degree of empiricism, range of applicability, model verification and experimental needs for a wide class of protected transients, in particular, natural circulation shutdown heat removal for both loop- and pool-type plants.
Date: January 1, 1982
Creator: Khatib-Rahbar, M.; Guppy, J.G. & Cerbone, R.J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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HTGR Fuel performance basis

Description: The safety characteristics of the high-temperature gas-cooled reactor (HTGR) during normal and accident conditions are determined in part by HTGR fuel performance. During normal operation, less than 0.1% fuel failure occurs, primarily from defective particles. This low fuel failure fraction limits circulating activity to acceptable levels. During severe accidents, the radiological consequence is influenced by high-temperature fuel particle behavior. An empirical fuel failure model, supported by… more
Date: May 1982
Creator: Shamasundar, B. I.; Stansfield, O. M. & Jensen, D. D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Two-dimensional modeling of sodium boiling transients in simulated LMFBR fuel bundles

Description: A two-dimensional code for analysis of sodium boiling in LMFBR fuel assemblies has been developed at ORNL. This code, THORAX, has been used to analyze tests in 19- and 61-pin electrically-heated, simulated LMFBR fuel assemblies in the THORS facility. THORAX has simulated well the transient growth of the two-dimensional boiling region and the resulting static flow instability leading to dryout. Extrapolation of results to a full size fuel pin bundle shows that two-dimensional effects are reduced… more
Date: January 1, 1982
Creator: Rose, S. D.; Dearing, J. F.; Carbajo, J. J.; Levin, A. E.; Montgomery, B. H. & Wantland, J. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Calculational advance in the modeling of fuel-coolant interactions. [LMFBR]

Description: A new technique is applied to numerically simulate a fuel-coolant interaction. The technique is based on the ability to calculate separate space- and time-dependent velocities for each of the participating components. In the limiting case of a vapor explosion, this framework allows calculation of the pre-mixing phase of film boiling and interpenetration of the working fluid by hot liquid, which is required for extrapolating from experiments to a reactor hypothetical accident. Qualitative result… more
Date: January 1, 1982
Creator: Bohl, W.R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Validation of the in-vessel energy balance module in SSC for natural circulation transients. [LMFBR]

Description: Recently, the in-vessel energy module of the Super System Code (SSC) which calculates the fuel pin, coolant, and stucture temperatures, was changed from an explicit finite difference procedure to an implicit weighted residuals procedure. SSC is a computer code for the analysis of plant wide transients in reactor systems. SSC is designed to be fast running, i.e., faster than real time, while providing detailed information if desired. Therefore, it was necessary to show that the new procedure was… more
Date: January 1, 1982
Creator: Horak, W.C.; Guppy, J.G. & Kennett, R.J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Experimental and analytical studies of sodium interactions with various concretes. [LMFBR]

Description: Mechanistic models of sodium/concrete interactions are described. The SCAM model of interactions with basaltic concrete is being verified by experiments. Modelling of sodium interactions with limestone concrete is still at a preliminary stage but shows promise of being able to predict quantitatively the experimental data. Comparisons with experimental data are presented.
Date: January 1, 1982
Creator: Suo-Anttila, A. & Smaardyk, J.E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Thermohydraulic Modeling and Simulation of Breeder Reactors

Description: This paper deals with the modeling and simulation of system-wide transients in LMFBRs. Unprotected events (i.e., the presumption of failure of the plant protection system) leading to core-melt are not considered in this paper. The existing computational capabilities in the area of protected transients in the US are noted. Various physical and numerical approximations that are made in these codes are discussed. Finally, the future direction in the area of model verification and improvements is d… more
Date: January 1, 1982
Creator: Agrawal, A. K.; Khatib-Rahbar, M.; Curtis, R. T.; Hetrick, D. L. & Girijashankar, P. V.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Simulation of LMFBR

Description: The title of this session is taken to imply the system-wide thermohydraulic simulation of liquid metal fast breeder reactors (LMFBR). One is interested in predicting the temperatures, pressures, and the coolant flow rates throughout the entire plant including the reactor core, the primary and secondary sodium heat transport circuits, the steam generating system as well as other auxiliary circuits. Such a simulation is needed for (1) scoping studies (i.e., in the pre-design phase of a plant), (2… more
Date: January 1, 1982
Creator: Agrawal, A. K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Summary of ORNL work on NRC-sponsored HTGR safety research, July 1974-September 1980

Description: A summary is presented of the major accomplishments of the Oak Ridge National Laboratory (ORNL) research program on High-Temperature Gas-Cooled Reactor (HTGR) safety. This report is intended to help the nuclear Regulatory Commission establish goals for future research by comparing the status of the work here (as well as at other laboratories) with the perceived safety needs of the large HTGR. The ORNL program includes extensive work on dynamics-related safety code development, use of codes for … more
Date: March 1, 1982
Creator: Ball, S. J.; Cleveland, J. C.; Conklin, J. C.; Delene, J. G.; Harrington, R. M.; Hatta, M. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Some aspects of fluid-structure coupling. [LMFBR]

Description: This paper primarily discusses the formulation used in an algorithm that couples three-dimensional hydrodynamic and structural domains. The fluid domain is governed by the Navier-Stokes equations, and the structural domain is governed by the equations of nonlinear structural dynamics. Here, both the fluid and structure are discretized using finite elements. The fluid is discretized with eight-noded quasi-Eulerian hexahedrons and the structural components are represented by Lagrangian triangular… more
Date: January 1, 1982
Creator: Kulak, R.F.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Multi-dimensional arbitrary Lagrangian-Eulerian method for dynamic fluid-structure interaction. [LMFBR]

Description: This paper describes an arbitrary Lagrangian-Eulerian method for analyzing fluid-structure interactions in fast-reactor containment with complex internal structures. The fluid transient can be calculated either implicitly or explicitly, using a finite-difference mesh with vertices that may be moved with the fluid (Lagrangian), held fixed (Eulerian), or moved in any other prescribed manner (hybrid Lagrangian Eulerian). The structural response is computed explicitly by two nonlinear, elastic-plas… more
Date: January 1, 1982
Creator: Wang, C. Y. & Zeuch, W. R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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PARET code and the analysis of the SPERT I transients

Description: The PARET code has been adapted for the testing of methods and models and for subsequent use in the analysis of transient behavior in research reactors. Comparisons with the experimental results from the SPERT-I transients are provided. The code has also been applied to the analysis of the IAEA 10 MW benchmark cores for protected and unprotected transients. The present version of the PARET code provides a convenient means of assessing the various models and correlations proposed for use in the … more
Date: January 1, 1982
Creator: Woodruff, W.L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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New aspects in the analysis of loss-of-flow transients for homogeneous and heterogeneous LMFBR cores

Description: This paper presents the results of analyses of unprotected loss-of-flow (LOF) transients which have been performed to date using the new SAS4A code system. Accident histories for homogeneous and heterogeneous demo-sized cores (300 MWe) are compared and emphasis is placed on phenomena occurring after the initiation of fuel motion as described by LEVITATE. LEVITATE is the SAS4A model for the analysis of fuel and cladding dynamics under loss-of-flow (LOF) conditions and is believed to be the most-… more
Date: January 1, 1982
Creator: Tentner, A.M. & Wider, H.U.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Two-Phase-Flow Models and Their Limitations

Description: An accurate prediction of transient two-phase flow is essential to safety analyses of nuclear reactors under accident conditions. The fluid flow and heat transfer encountered are often extremely complex due to the reactor geometry and occurrence of transient two-phase flow. Recently considerable progresses in understanding and predicting these phenomena have been made by a combination of rigorous model development, advanced computational techniques, and a number of small and large scale support… more
Date: January 1, 1982
Creator: Ishii, M. & Kocamustafaogullari, G.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Data acquisition for the Sodium Loop Safety Facility experiment P4. [LMFBR]

Description: Data acquisition for the Sodium Loop Safety Facility (SLSF) experiment P4 used three computers for the continuous collection of data and two computers for the routing and displaying of data. Four of these computer systems were located at the Engineering Test Reactor (ETR) site, in Idaho, to access sensor signals from the analog to digital interfaces. The fifth system was located at Argonne National Laboratory (ANL), in Illinois, and was used mainly for display and storage of data. All display c… more
Date: January 1, 1982
Creator: Baldwin, R. D.; Kraimer, M. R.; Wilson, R. E. & Gilbert, D. M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Transition from forced to natural convective flow in an LMFBR under adverse thermal conditions

Description: One of the most important aspects of the demonstration of the safety of liquid metal cooled fast reactors (LMFBR) is the assurance of adequate cooling of the reactor and critical structures during all potential or hypothetical events. To this end, a design philosophy has developed in which alternate heat removal systems are included in a plant in order to provide independent, diverse, and redundant cooling from the normal heat transport system. Recent studies have examined various aspects of na… more
Date: January 1, 1982
Creator: Singer, R. M.; Mohr, D. & Gillette, J. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Assessment of the thermal-hydraulic technology of the transition phase of a core-disruptive accident in a LMFBR

Description: The technology of thermal hydraulic aspects of the transition phase accident sequence in liquid metal fast breeder reactors has been reviewed. Previous analyses of the transition phase accident sequence have been reviewed and the current understanding of major thermal hydraulic phenomenology has been assessed. As a result of the foregoing, together with a scoping analysis of the transition phase accident sequence, major transition phase issues have been defined and research needs have been iden… more
Date: November 1982
Creator: Greene, G. A.; Ginsberg, T. & Kazimi, M. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SIMMER-II analysis of SRI postdisassembly expansion experiments. [LMFBR]

Description: Calculations of simulated postdisassembly expansions with SIMMER-II are compared to experimental data. The main features of the fluid motion are reproduced accurately. Good agreement is achieved for the important parameters of kinetic energy and impulse imparted to the vessel head. The most important calculated results are shown to be relatively insensitive to numerical modeling variations and uncertainties in many physical parameters. The geometric configuration of the upper internal structure… more
Date: August 1, 1982
Creator: Bott, T.F. & Bell, C.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PLUGM: a coupled thermal-hydraulic computer model for freezing melt flow in a channel. [LMFBR]

Description: PLUGM is a coupled thermal-hydraulic computer model for freezing liquid flow and plugging in a cold channel. PLUGM is being developed at Sandia National Laboratories for applications in Sandia's ex-vessel Core Retention Concept Assessment Program and in Sandia's LMFBR Transition Phase Program. The purpose of this paper is to introduce PLUGM and demonstrate how it can be used in the analysis of two of the core retention concepts under investigation at Sandia: refractory brick crucibles and parti… more
Date: January 1, 1982
Creator: Pilch, M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Statistical identification of effective input variables. [SCREEN]

Description: A statistical sensitivity analysis procedure has been developed for ranking the input data of large computer codes in the order of sensitivity-importance. The method is economical for large codes with many input variables, since it uses a relatively small number of computer runs. No prior judgemental elimination of input variables is needed. The sceening method is based on stagewise correlation and extensive regression analysis of output values calculated with selected input value combinations.… more
Date: September 1, 1982
Creator: Vaurio, J. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SIMMER analysis of SRI postdisassembly expansion experiments. [LMFBR]

Description: Calculations of simulated postdisassembly expansions with SIMMER-II are compared to experimental data. The main features of the fluid motion are reproduced accurately. Good agreement is achieved for the important parameters of kinetic energy and impulse imparted to the vessel head. The most important calculated results are shown to be relatively insensitive to numerical modeling variations and uncertainties in many physical parameters. The geometric configuration of the upper internal structure… more
Date: January 1, 1982
Creator: Bott, T.F. & Bell, C.R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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