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PACKAGE ID000735IBMPC00 PARET-ANL
KWIC TitleProgram for the Analysis of Reactor Transients 
AUTHORSW.L. Woodruff; R.S. Smith
LIMITATION/AUDIENCE CODEUNL/UNL
COMPLETION DATE01/29/2002 
PUBLICATION DATE01/29/2002 
DESCRIPTIONThis program is designed for use in predicting the course of and consequence of nondestructive accidents in research and test reactor cores. It is intended primarily for the analysis of plate type research and test reactors and has been subjected to extensive comparisons with the SPERT I and SPERT II experiments. These comparisons were quite favorable for a wide range of transients up to and including melting of the clad. Favorable comparisons have also been made for TRIGA reactor pulses in pin geometry. The PARET/ANL code has been used by the RERTR (Reduced Enrichment Research and Test Reactor) Program for the safety evaluation of many of the candidate reactors for reduced enrichment. 
PACKAGE CONTENTSMedia Directory; Software Abstract; Media includes Source Code, User Guide and ReadMe;/1 CD ROM 
SOURCE CODE INCLUDED?
MEDIA QUANTITY
METHOD OF SOLUTIONThe code provides a coupled thermal, hydrodynamic and point kinetics capability. The core can be represented by one to four regions. Each region may have different power generation, coolant mass flow rate and hydraulic parameters as represented by a single fuel pin or plate with associated coolant channel. The heat transfer in each fuel element is computed on the basis of a one-dimensional solution in each of up to 21 axial sections. The hydrodynamics solution is also one-dimensional for each channel at each time node. The heat transfer may take place by natural or forced convection, nucleate, transition or stable film boiling, and the cooling is allowed to range from sub-cooled liquid, through the two-phase regime, up to and including super-heated steam and may include coolant flow reversal. The code has an optional "voiding model" which estimates the voiding produced by sub-cooled boiling. 
COMPUTERIBM PC 
OPERATING SYSTEMSMicrosoft Windows 95, Windows 98, Windows NT or Linux on the personal computer and UNIX on the workstation. 
PROGRAMMING LANGUAGESFortran 77 
SOFTWARE LIMITATIONSThe PARET model is subject to several recognized limitations which may limit the applicability to certain specific problems, depending on the nature of the transient under consideration. The code employs steady-state heat transfer correlations which may prove unrealistic in certain transient situations. Any complete description of a severe transient must include provisions for some sort of thermal or hydraulic crisis. PARET is limited in predicting such crises by the fact that it employs only steady-state correlations (no transient correlations with demonstrated reliability have been developed) . Accurate descriptions of hydraulic instability depend upon accurate computation of transient pressure and flow fluctuations. PARET employs an incompressible model and a simplified void volume generation model with a homogeneous fluid. Also, the magnitude of local pressures predicted to accompany coolant expulsion is strongly affected by the number of axial sections chosen. The hydrodynamic output thus should be interpreted as a qualitative indication of a possible crisis rather than a reliable quantitative prediction. PARET is not applicable to either destructive excursions or situations in which there are space-time variations in the neutron flux. 
RELATED SOFTWAREThis code is an extension of the original PARET/ANL code (L4ESC Abstract 555) . The code system now includes a properties library generator for both light and heavy water coolants, and a postprocessing code for extracting selected data from a summary file for further analysis or plotting. 
REFERENCESW. L. Woodruff and R. S. Smith, "A Users Guide for the ANL Version of the PARET CODE, PARET/ANL (2001 Rev.)", ANL/RERTR/Tt4-16, March 2001. C. F. Obenchain, "PARET - A Program for the Analysis of Reactor Transients", IDO-l7282, January 1969. W. L. Woodruff, "A Kinetics and Thermal-hydraulics Capability for the Analysis of Research Reactors", Nucl. Tech., 64, Feb. 1984. 
HARDWARE REQSIBM-compatible personal computer with Intel or compatible CPU or UNIX workstations. 
ABSTRACT STATUSReleased As-Is 6-20-2007 
SPONSORDOE/NE 
RESEARCH ORGArgonne National Laboratory 
PACKAGE TYPEAS-IS 

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