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THERMAL HYDRAULIC ANALYSIS OF A GAS TEST LOOP SYSTEM

This paper discusses thermal hydraulic calculations for a Gas Test Loop (GTL) system designed to provide a high intensity fast-flux irradiation environment for testing fuels and materials for advanced concept nuclear reactors. To assess the performance of candidate reactor fuels, these fuels must be irradiated under actual fast reactor flux conditions and operating environments, preferably in an existing irradiation facility [1]. Potential users of the GTL include the Generation IV Reactor Prog… more

Date: November 1, 2005

Creator: Guillen, Donna Post & Fisher, James E.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Development and New Directions for the RELAP5-3D Graphical Users Interface

The direction of development for the RELAP5 Graphical User Interfaces (RGUI) has been extended. In addition to existing plans for displaying all aspects of RELAP5 calculations, the plan now includes plans to display the calculations of a variety of codes including SCDAP, RETRAN and FLUENT. Recent work has included such extensions along with the previously planned and user-requested improvements and extensions. Visualization of heat-structures has been added. Adaptations were made for another co… more

Date: September 1, 2001

Creator: Mesina, George Lee

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Java XMGR

The XMGR5 graphing package [1] for drawing RELAP5 [2] plots is being re-written in Java [3]. Java is a robust programming language that is available at no cost for most computer platforms from Sun Microsystems, Inc. XMGR5 is an extension of an XY plotting tool called ACE/gr extended to plot data from several US Nuclear Regulatory Commission (NRC) applications. It is also the most popular graphing package worldwide for making RELAP5 plots. In Section 1, a short review of XMGR5 is given, followed… more

Date: August 1, 2004

Creator: Mesina, Dr. George L. & Miller, Steven P.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Pygmalion Users Manual

PYGMALION (or Pygi for short) is a RELAP5 utility program that updates the initial condition information within a RELAP5 input file. These initial conditions are obtained by performing steady-state calculations, the final results of which are written to a restart/plot (rstplt) file for subsequent use. Pygi accesses the rstplt file, obtains the final conditions for each component of the system model, and replaces the appropriate cards in the original input file with cards containing the new cond… more

Date: August 1, 2001

Creator: Fisher, J. E.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Verification and Validation of Corrected Versions of RELAP5 for ATR Reactivity Analyses

Two versions of the RELAP5 computer code, RELAP5/MOD2.5 and RELAP5/MOD3 Version 3.2.1.2, are used to support safety analyses of the Advanced Test Reactor (ATR). Both versions of RELAP5 contain a point reactor kinetics model that has been used to simulate power excursion transients at the ATR. Errors in the RELAP5 point kinetics model were reported to the RELAP5 code developers in 2007. These errors had the potential to affect reactivity analyses that are part of the ATR’s safety basis. Conseque… more

Date: November 1, 2008

Creator: Davis, Cliff B.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Recent Improvements To The RELAP5-3D Code

The RELAP5-3D computer program has been recently improved. Changes were made as follows: (1) heat structures are allowed to be decoupled from hydrodynamic components, (2) built-in material properties for heat structures have been made consistent with those in MATPRO and the Nuclear Systems Materials Handbook (they are now documented in the RELAP5-3D manual, (3) Schrock's flow quality correlation is now used for a downward oriented junction from a horizontal volume for the stratification entrain… more

Date: June 1, 2006

Creator: Riemke, Richard A.; Bayless, Paul D. & Modro, S. Michael

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

RELAP5-3D User Problems

The Reactor Excursion and Leak Analysis Program with 3D capability1 (RELAP5-3D) is a reactor system analysis code that has been developed at the Idaho National Engineering and Environmental Laboratory (INEEL) for the U. S. Department of Energy (DOE). The 3D capability in RELAP5-3D includes 3D hydrodynamics2 and 3D neutron kinetics3,4. Assessment, verification, and validation of the 3D capability in RELAP5-3D is discussed in the literature5,6,7,8,9,10. Additional assessment, verification, and va… more

Date: September 1, 2002

Creator: Riemke, Richard Allan

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Implementation of DOWTHERM A Properties into RELAP5-3D/ATHENA

DOWTHERM A oil is being considered for use as a heat transfer fluid in experiments to help in the design of heat transfer components for the Next Generation Nuclear Plant (NGNP). In conjection with the experiments RELAP5-3D/ATHENA will be used to help design and analyzed the data generated by the experiments. Inorder to use RELAP5-3D the thermophysical properties of DOWTHERM A were implemented into the fluids package of the RELAP5-3D/ATHENA computer propgram. DOWTHERM A properties were implemen… more

Date: April 1, 2010

Creator: Moore, Richard L.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

PHISICS: New Features and Advancements

The PHISICS (Parallel and Highly Innovative Simulation for INL Code System) software is under an intensive development at INL. In the last months new features have been added and improvements of the previously existing one performed. The modular approach has created a friendly development environment that allows a quick expansion of the capabilities. In the last months a little amount of work has been dedicated to the improvement of the spherical harmonics based nodal transport solver while the… more

Date: June 1, 2011

Creator: Rabiti, C.; Wang, Y.; Palmiotti, G.; Hiruta, H.; Cogliati, J.; Alfonsi, A. et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Uncertainty Analysis for RELAP5-3D

In its current state, RELAP5-3D is a 'best-estimate' code; it is one of our most reliable programs for modeling what occurs within reactor systems in transients from given initial conditions. This code, however, remains an estimator. A statistical analysis has been performed that begins to lay the foundation for a full uncertainty analysis. By varying the inputs over assumed probability density functions, the output parameters were shown to vary. Using such statistical tools as means, variances… more

Date: August 1, 2011

Creator: Pawel, Aaron J. & Mesina, Dr. George L.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

RELAP5/MOD3.2 Assessment Using CHF Data from the KS-1 and V-200 Experiment Facilities

The RELAP/MOD3.2 computer code has been assessed using rod bundle critical heat flux data from the KS-1 and V-200 facilities. This work was performed as part of the U.S. Department of Energy’s International Nuclear Safety Program, and is part of the effort addressing the capability of the RELAP5/MOD3.2 code to model transients in Soviet-designed reactors. Designated VVER Standard Problem 7, these tests addressed one of the important phenomena related to VVER behavior that the code needs to simu… more

Date: July 1, 2001

Creator: Bayless, Paul David

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

RESTRUCTURING RELAP5-3D FOR NEXT GENERATION NUCLEAR PLANT ANALYSIS

RELAP5-3D is used worldwide for analyzing nuclear reactors under both operational transients and postulated accident conditions. Development of the RELAP code series began in 1975 and since that time the code has been continuously improved, enhanced, verified and validated [1]. Since RELAP5-3D will continue to be the premier thermal hydraulics tool well into the future, it is necessary to modernize the code to accommodate the incorporation of additional capabilities to support the development o… more

Date: June 1, 2006

Creator: Guillen, Donna Post; Mesina, George L. & Hykes, Joshua M.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

RGUI 1.0, New Graphical User Interface for RELAP5-3D

With the advent of three-dimensional modeling in nuclear safety analysis codes, the need has arisen for a new display methodology. Currently, analysts either sort through voluminous numerical displays of data at points in a region, or view color coded interpretations of the data on a two-dimensional rendition of the plant. RGUI 1.0 provides 3D capability for displaying data. The 3D isometric hydrodynamic image is built automatically from the input deck without additional input from the user. St… more

Date: April 1, 1999

Creator: Mesina, George Lee & Galbraith, James Andrew

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

RELAP5/MOD3.2 Assessment Using INSC SP-PSBV1

Assessments of the RELAP5/MOD3.2 computer code using loss-of-coolant experiment data from the PSB facility have been performed independently by analysts at the Electrogorsk Research and Engineering Center and the Idaho National Engineering and Environmental Laboratory. The PSB experiment facility is a full height, 1/300 volume and power scale representation of a VVER-1000 reactor. The experiment modeled was an 11% break in the upper plenum, simulating the rupture of one of the hydroaccumulator … more

Date: October 1, 2003

Creator: Bayless, P.; Melikhov, O.; Melikhov, V.; Parfenov, Yu.; Gavritenkova, O.; Elkin, I. et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Reformulation RELAP5-3D in FORTRAN 95 and Results

RELAP5-3D is a nuclear power plant code used worldwide for safety analysis, design, and operator training. In keeping with ongoing developments in the computing industry, we have re-architected the code in the FORTRAN 95 language, the current, fully-available, FORTRAN language. These changes include a complete reworking of the database and conversion of the source code to take advantage of new constructs. The improvements and impacts to the code are manifold. It is a completely machine-independ… more

Date: August 1, 2010

Creator: Mesina, Dr. George L

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

RGUI 1.0, New Graphical User Interface for RELAP5-3D

Date: April 1, 1999

Creator: Mesina, G. L. & Galbraith, J.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Thermal Response of the Hybrid Loop-Pool Design for Sodium Cooled Faster Reactors

An innovative hybrid loop-pool design for the sodium cooled fast reactor (SFR) has been recently proposed with the primary objective of achieving cost reduction and safety enhancement. With the hybrid loop-pool design, closed primary loops are immersed in a secondary buffer tank. This design takes advantage of features from conventional both pool and loop designs to further improve economics and safety. This paper will briefly introduce the hybrid loop-pool design concept and present the calcul… more

Date: September 1, 2008

Creator: Zhang, Hongbin; Zhao, Haihua & Davis, Cliff

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

RCCS Experiments and Validation for High Temperature Gas-Cooled Reactor

A reactor cavity cooling system (RCCS), an air-cooled helical coil RCCS unit immersed in the water pool, was proposed to overcome the disadvantages of the weak cooling ability of air-cooled RCCS and the complex structure of water-cooled RCCS for the high temperature gas-cooled reactor (HTGR). An experimental apparatus was constructed to investigate the various heat transfer phenomena in the water pool type RCCS, such as the natural convection of air inside the cavity, radiation in the cavity, t… more

Date: September 1, 2007

Creator: Oh, Chang; Davis, Cliff & Park, Goon C.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Extensions to SCDAP/RELAP5/ATHENA for Analysis of HTGRs and SCWRs

The SCDAP/RELAP5/ATHENA code was extended to enable the code to perform transient analyses of High Temperature Gas Reactors (HTGRs). Preliminary results indicate that post-shutdown decay heat can be adequately removed from HTGRs by natural circulation of atmospheric air.

Date: April 1, 2004

Creator: Harvego, E. A. & Siefken, L. J.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Hot Zero and Full Power Validation of PHISICS RELAP-5 Coupling

PHISICS is a reactor analysis toolkit developed in the last 3 years at the Idaho National Laboratory that has been also coupled with the thermo-hydraulic plant simulator RELAP5-3D. PHISICS is aimed to provide an optimal trade off between needed computational resources and accuracy in the range of 10~100 cores. In fact this range has been identified as the next 5 to 10 years average computational capability available to nuclear engineer designing and optimizing nuclear reactor cores. Different p… more

Date: June 1, 2013

Creator: Lodi, F.; Rabiti, C.; Alfonsi, A.; Epiney, A. & Sumini, M.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Improved Accuracy for Two-Phase Downflow Scenarios

Problems have been reported for very high downflows in small and intermediate pipes in the bubbly and slug flow regimes. When the flow rate is near critical, the calculated mass flow rate depends strongly on the flow orientation for small and intermediate pipes, whereas the flow rate is nearly independent of flow direction for large pipes. At very high flow rates, the flow is expected to be nearly homogenous and hence to be nearly independent of flow direction. The flow rates calculated by RELA… more

Date: October 1, 2012

Creator: Davis, Cliff B.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Evaluation of Fluid Conduction and Mixing within a Subassembly of the Actinide Burner Test Reactor

The RELAP5-3D code is being considered as a thermal-hydraulic system code to support the development of the sodium-cooled Actinide Burner Test Reactor as part of the Global Nuclear Energy Partnership. An evaluation was performed to determine whether the control system could be used to simulate the effects of non-convective mechanisms of heat transport in the fluid, including axial and radial heat conduction and subchannel mixing, that are not currently represented with internal code models. The… more

Date: September 1, 2007

Creator: Davis, Cliff B.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Applicability of RELAP5-3D for Thermal-Hydraulic Analyses of a Sodium-Cooled Actinide Burner Test Reactor

The Actinide Burner Test Reactor (ABTR) is envisioned as a sodium-cooled, fast reactor that will burn the actinides generated in light water reactors to reduce nuclear waste and ease proliferation concerns. The RELAP5-3D computer code is being considered as the thermal-hydraulic system code to support the development of the ABTR. An evaluation was performed to determine the applicability of RELAP5-3D for the analysis of a sodium-cooled fast reactor. The applicability evaluation consisted of sev… more

Date: July 1, 2006

Creator: Davis, C. B.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

RELAP5-3D Developmental Assessment: Comparison of Versions 4.0.3is and 2.4.2is

Figures have been generated comparing the parameters used in the developmental assessment of the RELAP5-3D code using versions 4.0.3is and 2.4.2is. The figures, which are the same as those used in Volume III of the RELAP5-3D code manual, compare calculations using the semi-implicit solution scheme with available experiment data. These figures provide a quick, visual indication of how the code predictions changed between these two code versions and can be used to identify cases in which the asse… more

Date: September 1, 2012

Creator: Bayless, Paul D.

Item Type: Report

Partner: UNT Libraries Government Documents Department