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TRAC-PF1: an advanced best-estimate computer program for pressurized water reactor analysis

Description: The Transient Reactor Analysis Code (TRAC) is being developed at the Los Alamos National Laboratory to provide advanced best-estimate predictions of postulated accidents in light water reactors. The TRAC-PF1 program provides this capability for pressurized water reactors and for many thermal-hydraulic experimental facilities. The code features either a one-dimensional or a three-dimensional treatment of the pressure vessel and its associated internals; a two-phase, two-fluid nonequilibrium hydr… more
Date: February 1, 1984
Creator: Liles, D.R. & Mahaffy, J.H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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TOPAZ: a computer code for modeling heat transfer and fluid flow in arbitrary networks of pipes, flow branches, and vessels

Description: An overview of the computer code TOPAZ (Transient-One-Dimensional Pipe Flow Analyzer) is presented. TOPAZ models the flow of compressible and incompressible fluids through complex and arbitrary arrangements of pipes, valves, flow branches and vessels. Heat transfer to and from the fluid containment structures (i.e. vessel and pipe walls) can also be modeled. This document includes discussions of the fluid flow equations and containment heat conduction equations. The modeling philosophy, numeric… more
Date: January 1, 1984
Creator: Winters, W.S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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TRAC-PF1/MOD1 computer code

Description: The TRAC-P1 program was designed primarily for the analysis of large-break loss-of-coolant accidents (LOCAs) in pressurized water reactors (PWRs). Because of its versatility, however, it can be applied directly to many analyses ranging from blowdowns in simple pipes to integral LOCA tests in multiloop facilities. A refined version, called TRAC-P1A, was released to the National Energy Software Center (NESC) in March 1979. Although it still treats the same class of problems, TRAC-P1A is more effi… more
Date: January 1, 1984
Creator: Liles, D.R. & Mahaffy, J.H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Assessment of TRAC-BD1 amd RAMONA-3B codes fpr BWR ATWS application

Description: Based on comparisons between the TRAC-BD1 power imposed calculation and the RAMONA-3B results, it can be said that the thermal-hydraulic models of both RAMONA-3B and TRAC-BD1 provide adequate representation of an ATWS event in a BWR. However, for the reactor power calculation, RAMONA-3B with space-time neutron kinetics is a superior and preferable tool to the TRAC-BD1 with point kinetics for ATWS type events where the spatial core power distribution varies with time. Also, the computer running … more
Date: January 1, 1984
Creator: Neymotin, L.; Hsu, C.J. & Saha, P.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Two-dimensional modeling of sodium boiling in a simulated LMFBR loss-of-flow test

Description: Loss-of-flow (LOF) accidents are of major importance in LMFBR safety. Tests have been performed to simulate the simultaneous failure of all primary pumps and reactor shutdown systems in a 37-pin electrically heated test bundle installed in the KNS sodium boiling loop at the Institute of Reactor Development, Karlsruhe. The tests simulated LOF conditions of the German prototype LMFBR, the SNR 300. The main objectives of these tests were to characterize the transient boiling development to claddin… more
Date: January 1, 1984
Creator: Rose, S.D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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User's guide for TWOHEX: a code package for two-dimensional, neutral-particle transport in equilateral triangular meshes

Description: TWOHEX solves the two-dimensional multigroup transport equation on an equilateral triangular mesh in the x,y plane. Both regular and adjoint, inhomogeneous (fixed source) and homogeneous problems are solved. Three problem domains are treated by TWOHEX. The whole core domain is a 60/sup 0/ parallelogram with vacuum boundary conditions on each face. The third core domain is a 120/sup 0/ parallelogram with two vacuum and two rotational boundary conditions. The sixth core domain is a 60/sup 0/ para… more
Date: October 1, 1984
Creator: Walters, W. F.; Brinkley, F. W. & Marr, D. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

TACI: a code for interactive analysis of neutron data produced by a tissue equivalent proportional counter

Description: The TEPC analysis code (TACI) is a computer program designed to analyze pulse height data generated by a tissue equivalent proportional counter (TEPC). It is written in HP BASIC and is for use on an HP-87XM personal computer. The theory of TEPC analysis upon which this code is based is summarized.
Date: June 1, 1984
Creator: Cummings, F.M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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TWIST: a Transient Two-dimensional Intra-Subassembly Thermal-Hydraulics model for LMFBRs

Description: It is concluded that due to physical accuracy and numerical efficiency (5 to 10 times faster than real time) of this model, it provides an excellent tool for study of long duration natural circulation transients in LMFBR assemblies.
Date: January 1, 1984
Creator: Khatib-Rahbar, M. & Cazzoli, E. G.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

TRAC-PF1 analyses of potential pressurized-thermal-shock transients at a Combustion-Engineering PWR. [Overcooling]

Description: Los Alamos is participating in a program to assess the risk of pressurized thermal shock (PTS) to a reactor vessel. Our role is to provide best-estimate thermal-hydraulic analyses of 12 postulated overcooling transients using TRAC-PF1. These transients are hypothetical and include multiple operator/equipment failures. Calvert Cliffs/Unit-1, a Combustion-Engineering plant, is the pressurized water reactor modeled for this study. The utility and the vendor supplied information for the comprehensi… more
Date: January 1, 1984
Creator: Koenig, J. E.; Spriggs, G. D. & Smith, R. C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

TRAC-PF1/MOD1 assessment at Los Alamos

Description: The Los Alamos National Laboratory is developing the Transient Reactor Analysis Code (TRAC) to provide an advanced best-estimate predictive capability for the analysis of postulated accidents in pressurized water reactors (PWRs). Over the past several years, four distinct versions of the code have been released; each new version introduced improvements to the existing models and numerics and added new models to extend the applications of the code. The first goal of the code was to analyze large… more
Date: January 1, 1984
Creator: Knight, T. D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Status and application of TRAC-BD1/MOD1 to benchmark data

Description: The TRAC-BD1/MOD1 code can simulate a full range of operational transients and postulated accidents. It has been tested against a range of separate effects and systems test data and the agreement between the code simulation and the test data is good overall but specific areas of improvement remain. Work currently underway includes the development of a one-dimensional neutron kinetics model and a Courant limit violating numerical scheme to increase the computational speed of the code for simulat… more
Date: January 1, 1984
Creator: Weaver, W. L., III
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Implementation of empirical total pressure loss data into the DUCTFLO and TOPAZ gas transfer codes

Description: Sandia presently has two computer codes capable of modeling local pressure and enthalpy losses in lines connecting gas reservoirs and receivers. Each code conserves flow continuity, momentum, and energy as a function of position along the flow path. The first of these codes, DUCTFLO, models gas flow by solving a set of coupled algebraic equations. The DUCTFLO code has been formulated to make direct use of laboratory total pressure and enthalpy loss data. The second code, TOPAZ, models gas flow … more
Date: November 1, 1984
Creator: Winters, W.S. & Kanouff, M.P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

THR-TH: a high-temperature gas-cooled nuclear reactor core thermal hydraulics code

Description: The ORNL version of PEBBLE, the (RZ) pebble bed thermal hydraulics code, has been extended for application to a prismatic gas cooled reactor core. The supplemental treatment is of one-dimensional coolant flow in up to a three-dimensional core description. Power density data from a neutronics and exposure calculation are used as the basic information for the thermal hydraulics calculation of heat removal. Two-dimensional neutronics results may be expanded for a three-dimensional hydraulics calcu… more
Date: July 1, 1984
Creator: Vondy, D.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

PWR plant transient analyses using TRAC-PF1

Description: This paper describes some of the pressurized water reactor (PWR) transient analyses performed at Los Alamos for the US Nuclear Regulatory Commission using the Transient Reactor Analysis Code (TRAC-PF1). Many of the transient analyses performed directly address current PWR safety issues. Included in this paper are examples of two safety issues addressed by TRAC-PF1. These examples are pressurized thermal shock (PTS) and feed-and-bleed cooling for Oconee-1. The calculations performed were plant s… more
Date: January 1, 1984
Creator: Ireland, J. R. & Boyack, B. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

TERRA: a computer code for simulating the transport of environmentally released radionuclides through agriculture

Description: TERRA is a computer code which calculates concentrations of radionuclides and ingrowing daughters in surface and root-zone soil, produce and feed, beef, and milk from a given deposition rate at any location in the conterminous United States. The code is fully integrated with seven other computer codes which together comprise a Computerized Radiological Risk Investigation System, CRRIS. Output from either the long range (> 100 km) atmospheric dispersion code RETADD-II or the short range (<80 km)… more
Date: November 1, 1984
Creator: Baes, C. F., III; Sharp, R. D.; Sjoreen, A. L. & Hermann, O. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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