RELAP5-3D is a

simulation A simulation is the imitation of the operation of a real-world process or system over time. Simulations require the use of models; the model represents the key characteristics or behaviors of the selected system or process, whereas the ...

tool that allows users to

model A model is an informative representation of an object, person or system. The term originally denoted the plans of a building in late 16th-century English, and derived via French and Italian ultimately from Latin ''modulus'', a measure. Models c ...

the coupled behavior of the reactor coolant system and the

core Core or cores may refer to: Science and technology * Core (anatomy), everything except the appendages * Core (manufacturing), used in casting and molding * Core (optical fiber), the signal-carrying portion of an optical fiber * Core, the centra ...

for various operational transients and postulated

accidents An accident is an unintended, normally unwanted event that was not directly caused by humans. The term ''accident'' implies that nobody should be blamed, but the event may have been caused by unrecognized or unaddressed risks. Most researche ...

that might occur in a

nuclear reactor A nuclear reactor is a device used to initiate and control a fission nuclear chain reaction or nuclear fusion reactions. Nuclear reactors are used at nuclear power plants for electricity generation and in nuclear marine propulsion. Heat from nu ...

. RELAP5-3D (Reactor Excursion and Leak Analysis Program) can be used for reactor safety analysis, reactor design, simulator training of operators, and as an educational tool by universities. RELAP5-3D was developed at

Idaho National Laboratory Idaho National Laboratory (INL) is one of the national laboratories of the United States Department of Energy and is managed by the Battelle Energy Alliance. While the laboratory does other research, historically it has been involved with nu ...

to address the pressing need for reactor safety analysis and continues to be developed through the

United States Department of Energy The United States Department of Energy (DOE) is an executive department of the U.S. federal government that oversees U.S. national energy policy and manages the research and development of nuclear power and nuclear weapons in the United Stat ...

and the International RELAP5 Users Group (IRUG) with over $3 million invested annually. The code is distributed through INL's Technology Deployment Office and is licensed to numerous

universities A university () is an institution of higher (or tertiary) education and research which awards academic degrees in several academic disciplines. ''University'' is derived from the Latin phrase ''universitas magistrorum et scholarium'', which ...

governments A government is the system or group of people governing an organized community, generally a state. In the case of its broad associative definition, government normally consists of legislature, executive, and judiciary. Government is ...

, and

corporations A corporation is an organization—usually a group of people or a company—authorized by the state to act as a single entity (a legal entity recognized by private and public law "born out of statute"; a legal person in legal context) and ...

worldwide.

Background

RELAP5-3D is an outgrowth of the one-dimensional RELAP5/MOD3 code developed at

(INL) for the U.S.

Nuclear Regulatory Commission The Nuclear Regulatory Commission (NRC) is an independent agency of the United States government tasked with protecting public health and safety related to nuclear energy. Established by the Energy Reorganization Act of 1974, the NRC began oper ...

(NRC). The U.S. Department of Energy (DOE) began sponsoring additional RELAP5 development in the early 1980s to meet its own reactor safety assessment needs. Following the

Chernobyl disaster The Chernobyl disaster was a nuclear accident that occurred on 26 April 1986 at the No. 4 nuclear reactor, reactor in the Chernobyl Nuclear Power Plant, near the city of Pripyat in the north of the Ukrainian Soviet Socialist Republic, Ukrainia ...

, DOE undertook a re-assessment of the safety of all its test and production reactors throughout the

United States The United States of America (U.S.A. or USA), commonly known as the United States (U.S. or US) or America, is a country primarily located in North America. It consists of 50 U.S. state, states, a Washington, D.C., federal district, five ma ...

. The RELAP5 code was chosen as the thermal-hydraulic analysis tool because of its widespread acceptance. The application of RELAP5 to various reactor designs created the need for new

modeling A model is an informative representation of an object, person or system. The term originally denoted the plans of a building in late 16th-century English, and derived via French and Italian ultimately from Latin ''modulus'', a measure. Models c ...

capabilities. In particular, the analysis of the Savannah River reactors necessitated a three-dimensional flow model. Later, under laboratory-discretionary funding, multi-dimensional reactor kinetics were added. Up until the end of 1995, INL maintained NRC and DOE versions of the code in a single

source code In computing, source code, or simply code, is any collection of code, with or without comment (computer programming), comments, written using a human-readable programming language, usually as plain text. The source code of a Computer program, p ...

that could be partitioned before compilation. It became clear by then, however, that the efficiencies realized by the maintenance of a single source were being overcome by the extra effort required to accommodate sometimes conflicting requirements. The code was therefore "

split Split(s) or The Split may refer to: Places * Split, Croatia, the largest coastal city in Croatia * Split Island, Canada, an island in the Hudson Bay * Split Island, Falkland Islands * Split Island, Fiji, better known as Hạfliua Arts, entertain ...

" into two

versions Version may refer to: Computing * Software version, a set of numbers that identify a unique evolution of a computer program * VERSION (CONFIG.SYS directive), a configuration directive in FreeDOS Music * Cover version * Dub version * Remix * ''Ve ...

—one for NRC and the other for DOE. The DOE version maintained all of the capabilities and validation history of the predecessor code, plus the added capabilities that had been sponsored by the DOE before and after the split. The most prominent attribute that distinguishes the DOE code from the NRC code is the fully integrated, multi-dimensional thermal-hydraulic and kinetic modeling capability in the DOE code. This removes any restrictions on the applicability of the code to the full range of postulated reactor accidents. Other enhancements include a new

matrix Matrix most commonly refers to: * ''The Matrix'' (franchise), an American media franchise ** '' The Matrix'', a 1999 science-fiction action film ** "The Matrix", a fictional setting, a virtual reality environment, within ''The Matrix'' (franchi ...

solver, additional water properties, and improved time advancement for greater

robustness Robustness is the property of being strong and healthy in constitution. When it is transposed into a system, it refers to the ability of tolerating perturbations that might affect the system’s functional body. In the same line ''robustness'' ca ...

Features

Modeling Capability

RELAP5-3D has multidimensional

thermal hydraulics Thermal hydraulics (also called thermohydraulics) is the study of hydraulic flow in thermal fluids. The area can be mainly divided into three parts: thermodynamics, fluid mechanics, and heat transfer, but they are often closely linked to each other ...

and

neutron The neutron is a subatomic particle, symbol or , which has a neutral (not positive or negative) charge, and a mass slightly greater than that of a proton. Protons and neutrons constitute the nuclei of atoms. Since protons and neutrons behav ...

kinetic modeling capabilities. The multidimensional component in RELAP5-3D was developed to allow the user to accurately model the multidimensional

flow Flow may refer to: Science and technology * Fluid flow, the motion of a gas or liquid * Flow (geomorphology), a type of mass wasting or slope movement in geomorphology * Flow (mathematics), a group action of the real numbers on a set * Flow (psyc ...

behavior that can be exhibited in any component or region of a nuclear reactor coolant system. There is also two dimensional

conductive In physics and electrical engineering, a conductor is an object or type of material that allows the flow of charge (electric current) in one or more directions. Materials made of metal are common electrical conductors. Electric current is gen ...

and radiative

heat transfer Heat transfer is a discipline of thermal engineering that concerns the generation, use, conversion, and exchange of thermal energy (heat) between physical systems. Heat transfer is classified into various mechanisms, such as thermal conduction ...

capability and modeling of plant trips and control systems. RELAP5-3D allows for the simulation of the full range of reactor transients and postulated accidents, including: *

Trips The Agreement on Trade-Related Aspects of Intellectual Property Rights (TRIPS) is an international legal agreement between all the member nations of the World Trade Organization (WTO). It establishes minimum standards for the regulation by nat ...

and controls * Component models (

pumps A pump is a device that moves fluids ( liquids or gases), or sometimes slurries, by mechanical action, typically converted from electrical energy into hydraulic energy. Pumps can be classified into three major groups according to the method the ...

, valves, separators, branches, etc.) * Operational transients * Startup and

shutdown Shutdown or shut down may refer to: * Government shutdowns in the United States * Shutdown (computing) * Shutdown (economics) * Shutdown (nuclear reactor) Arts and entertainment Music * "Shut Down" (The Beach Boys song), 1963 * ''Shut Down Volu ...

* Maneuvers (e.g. change in power level, starting/tripping pump) * Small and large break Loss Of Coolant Accidents (LOCA) * Anticipated Transient Without

Scram A scram or SCRAM is an emergency shutdown of a nuclear reactor effected by immediately terminating the fission reaction. It is also the name that is given to the manually operated kill switch that initiates the shutdown. In commercial reactor ...

(ATWS) * Loss of offsite power * Loss of

feedwater Boiler feedwater is an essential part of boiler operations. The feed water is put into the steam drum from a feed pump. In the steam drum the feed water is then turned into steam from the heat. After the steam is used it is then dumped to the m ...

* Loss of flow * Light Water Reactors ( PWR,

BWR A boiling water reactor (BWR) is a type of light water nuclear reactor used for the generation of electrical power. It is a design different from a Soviet graphite-moderated RBMK. It is the second most common type of electricity-generating nuc ...

APWR The Mitsubishi advanced pressurized water reactor (APWR) is a generation III nuclear reactor design developed by Mitsubishi Heavy Industries (MHI) based on pressurized water reactor technology. It features several design enhancements including a n ...

ABWR The advanced boiling water reactor (ABWR) is a Generation III boiling water reactor. The ABWR is currently offered by GE Hitachi Nuclear Energy (GEH) and Toshiba. The ABWR generates electrical power by using steam to power a turbine connected ...

, etc.) * Heavy Water Reactors (e.g.

CANDU reactor The CANDU (Canada Deuterium Uranium) is a Canadian pressurized heavy-water reactor design used to generate electric power. The acronym refers to its deuterium oxide ( heavy water) moderator and its use of (originally, natural) uranium fuel. ...

) * Gas-cooled Reactors ( VHTGR, NGNP) *

Liquid metal cooled reactor A liquid metal cooled nuclear reactor, liquid metal fast reactor or LMFR is an advanced type of nuclear reactor where the primary coolant is a liquid metal. Liquid metal cooled reactors were first adapted for nuclear submarine use and have been ...

s * Molten-salt cooled reactors

Hydrodynamic Model

RELAP5-3D is a transient, two-fluid model for flow of a two-phase

vapor In physics, a vapor (American English) or vapour (British English and Canadian English; see spelling differences) is a substance in the gas phase at a temperature lower than its critical temperature,R. H. Petrucci, W. S. Harwood, and F. G. H ...

gas Gas is one of the four fundamental states of matter (the others being solid, liquid, and plasma). A pure gas may be made up of individual atoms (e.g. a noble gas like neon), elemental molecules made from one type of atom (e.g. oxygen), or ...

liquid A liquid is a nearly incompressible fluid that conforms to the shape of its container but retains a (nearly) constant volume independent of pressure. As such, it is one of the four fundamental states of matter (the others being solid, gas, an ...

mixture that can contain non-condensable components in the vapor/gas phase and/or a

soluble In chemistry, solubility is the ability of a substance, the solute, to form a solution with another substance, the solvent. Insolubility is the opposite property, the inability of the solute to form such a solution. The extent of the solub ...

component in the

phase. The multi-dimensional component in RELAP5-3D was developed to allow the user to more accurately model the multi-dimensional flow behavior that can be exhibited in any component or region of an LWR system. Typically, this will be the lower

plenum Plenum may refer to: * Plenum chamber, a chamber intended to contain air, gas, or liquid at positive pressure * Plenism, or ''Horror vacui'' (physics) the concept that "nature abhors a vacuum" * Plenum (meeting), a meeting of a deliberative asse ...

, upper plenum and downcomer regions of an LWR. However, the model is general, and is not restricted to use in the

reactor vessel A reactor pressure vessel (RPV) in a nuclear power plant is the pressure vessel containing the nuclear reactor coolant, core shroud, and the reactor core. Classification of nuclear power reactors Russian Soviet era RBMK reactors have each fuel ...

. The component defines a one, two, or three-dimensional array of volumes and the internal junctions connecting them. The geometry can be either Cartesian (x, y, z) or cylindrical ( r, q, z). An orthogonal, three-dimensional grid is defined by mesh interval input data in each of the three coordinate directions. The functionality of the multi-dimensional component has been under testing and refinement since it was first applied to study the K reactor at Savannah River in the early 1990s. A set of ten verification test cases with closed form solutions are used to demonstrate the correctness of the numerical formulation for the conservation equations. Recent developments have updated the

programming language A programming language is a system of notation for writing computer programs. Most programming languages are text-based formal languages, but they may also be graphical. They are a kind of computer language. The description of a programming l ...

to FORTRAN 95 and incorporated

viscous The viscosity of a fluid is a measure of its resistance to deformation at a given rate. For liquids, it corresponds to the informal concept of "thickness": for example, syrup has a higher viscosity than water. Viscosity quantifies the inte ...

effects in multi-dimensional

hydrodynamic In physics and engineering, fluid dynamics is a subdiscipline of fluid mechanics that describes the flow of fluids—liquids and gases. It has several subdisciplines, including ''aerodynamics'' (the study of air and other gases in motion) and ...

models. Currently, RELAP5-3D contains 27 different working fluids including: * Light water (e.g. 1967, 1984, and 1995 steam tables) * Heavy water *

Gases Gas is one of the four fundamental states of matter (the others being solid, liquid, and plasma). A pure gas may be made up of individual atoms (e.g. a noble gas like neon), elemental molecules made from one type of atom (e.g. oxygen), ...

(e.g.

helium Helium (from el, ἥλιος, helios, lit=sun) is a chemical element with the symbol He and atomic number 2. It is a colorless, odorless, tasteless, non-toxic, inert, monatomic gas and the first in the noble gas group in the periodic table. ...

and

carbon dioxide Carbon dioxide ( chemical formula ) is a chemical compound made up of molecules that each have one carbon atom covalently double bonded to two oxygen atoms. It is found in the gas state at room temperature. In the air, carbon dioxide is t ...

) *

Molten salt Molten salt is salt which is solid at standard temperature and pressure but enters the liquid phase due to elevated temperature. Regular table salt has a melting point of 801 °C (1474°F) and a heat of fusion of 520 J/g.Proc. Roy. Soc. Bibli ...

s (e.g.

FLiBe FLiBe is a molten salt made from a mixture of lithium fluoride (LiF) and beryllium fluoride (BeF2). It is both a nuclear reactor coolant and solvent for fertile or fissile material. It served both purposes in the Molten-Salt Reactor Experim ...

and

FLiNaK FLiNaK is the name of the ternary eutectic alkaline metal fluoride salt mixture LiF- NaF- KF (46.5-11.5-42 mol %). It has a melting point of 454 °C and a boiling point of 1570 °C. It is used as electrolyte for the electroplatin ...

) *

Liquid metal A liquid metal is a metal or a metal alloy which is liquid at or near room temperature. The only stable liquid elemental metal at room temperature is mercury (Hg), which is molten above −38.8 °C (234.3 K, −37.9 °F). Three more ...

s (e.g.

sodium Sodium is a chemical element with the symbol Na (from Latin ''natrium'') and atomic number 11. It is a soft, silvery-white, highly reactive metal. Sodium is an alkali metal, being in group 1 of the periodic table. Its only stable ...

and

lead-bismuth eutectic Lead-Bismuth Eutectic or LBE is a eutectic alloy of lead (44.5 at%) and bismuth (55.5 at%) used as a coolant in some nuclear reactors, and is a proposed coolant for the lead-cooled fast reactor, part of the Generation IV reactor initiative. It ...

) * Alternative fluids (e.g.

glycerin Glycerol (), also called glycerine in British English and glycerin in American English, is a simple triol compound. It is a colorless, odorless, viscous liquid that is sweet-tasting and non-toxic. The glycerol backbone is found in lipids know ...

and

ammonia Ammonia is an inorganic compound of nitrogen and hydrogen with the formula . A stable binary hydride, and the simplest pnictogen hydride, ammonia is a colourless gas with a distinct pungent smell. Biologically, it is a common nitrogeno ...

) *

Refrigerants A refrigerant is a working fluid used in the refrigeration cycle of air conditioning systems and heat pumps where in most cases they undergo a repeated phase transition from a liquid to a gas and back again. Refrigerants are heavily regulated ...

(e.g.

R-134a 1,1,1,2-Tetrafluoroethane (also known as norflurane (INN), R-134a, Freon 134a, Forane 134a, Genetron 134a, Green Gas, Florasol 134a, Suva 134a, or HFC-134a) is a hydrofluorocarbon (HFC) and haloalkane refrigerant with thermodynamic properties s ...

) Working fluids allow single-phase, two-phase, and supercritical applications.

Thermal Model

Heat structures provided in RELAP5-3D permit calculation of heat transferred across solid boundaries of hydrodynamic volumes. Modeling capabilities of heat structures are general and include fuel pins or plates with nuclear or electrical heating, heat transfer across

steam generator A Steam generator is a device used to boil water to create steam. More specifically, it may refer to: *Boiler (steam generator), a closed vessel in which water is heated under pressure * Monotube steam generator *Supercritical steam generator or Be ...

tubes, and heat transfer from pipe and vessel walls. Temperature-dependent and space-dependent thermal conductivities and volumetric heat capacities are provided in tabular or functional form either from built-in or user-supplied data. There is also a radiative/conductive enclosure model, for which the user may supply/view conductance factors.

Control System

RELAP5-3D allows the user to model a control system typically used in hydrodynamic systems, including other phenomena described by algebraic and ordinary

differential equations In mathematics, a differential equation is an equation that relates one or more unknown functions and their derivatives. In applications, the functions generally represent physical quantities, the derivatives represent their rates of change, a ...

. Each control system component defines a variable as a specific function of time-advanced quantities; this permits control variables to be developed from components that perform simple, basic operations.

Reactor Kinetics

There are two options that include a point reactor kinetics model and a multidimensional neutron kinetics model. A flexible

neutron cross section In nuclear physics, the concept of a neutron cross section is used to express the likelihood of interaction between an incident neutron and a target nucleus. The neutron cross section σ can be defined as the area in cm2 for which the number of ...

model and a

control rod Control rods are used in nuclear reactors to control the rate of fission of the nuclear fuel – uranium or plutonium. Their compositions include chemical elements such as boron, cadmium, silver, hafnium, or indium, that are capable of absorbing ...

model have been implemented to allow for the complete modeling of the

reactor core A nuclear reactor core is the portion of a nuclear reactor containing the nuclear fuel components where the nuclear reactions take place and the heat is generated. Typically, the fuel will be low-enriched uranium contained in thousands of indi ...

. The

decay heat Decay heat is the heat released as a result of radioactive decay. This heat is produced as an effect of radiation on materials: the energy of the alpha, beta or gamma radiation is converted into the thermal movement of atoms. Decay heat occurs n ...

model developed as part of the point reactor kinetics model has been modified to compute decay power for point reactor kinetics and multi-dimensional neutron kinetics models.

Recent Major Upgrades

Accurate Verification Capability

Verification ensures the program is built right by: (1) showing it meets its design specifications, (2) comparing its calculations against analytical solutions and method of manufactured solutions. RELAP5-3D Sequential Verification writes a file of extremely accurate representations of primary variables for comparing calculations between code versions to reveal any changes. The test suite of input models exercise code capabilities important for modeling nuclear plants. This verification capability also provides means to test that important code functions such as restart and backup work properly.

Moving System Modeling Capability

The ability to simulate movement, such as could be encountered in ships, airplanes, or a terrestrial reactor during an earthquake becomes available in the 2013 release of RELAP5-3D. This capability allows the user to simulate motion through input, including translational displacement and rotation about the origin implied by the position of the reference volume. The transient rotation can be input using either Euler or pitch-yaw-roll angles. The movement is simulated using a combination of sine functions and tables of rotational angles and translational displacement. Since the gravitational constant is also an input quantity, this capability is not limited to the surface of the Earth. It allows RELAP5-3D to model reactor systems on space craft, a space station, the moon, or other extraterrestrial bodies.

International RELAP5 Users Group

There are five different levels of membership available in the International RELAP5 Users Group (IRUG). Each has a different level of benefits, services, and membership fee.

Members

A full member organization is the highest level of participation possible in the IRUG. Members receive the RELAP5-3D software in

form. Multiple copy use is allowed. Two levels of membership are available: Regular and "Super User". Regular Member organizations receive up to 40 hours of on-call assistance in areas such as model noding, code usage recommendations,

debugging In computer programming and software development, debugging is the process of finding and resolving ''bugs'' (defects or problems that prevent correct operation) within computer programs, software, or systems. Debugging tactics can involve in ...

, and interpretations of results from INL RELAP5 technical experts. Super Users receive up to 100 hours of staff assistance.

Multi-Use Participants

Multi-use participants are organizations that require use of the code but do not need or desire all the benefits of a full member. Participants receive the RELAP5-3D software in

executable In computing, executable code, an executable file, or an executable program, sometimes simply referred to as an executable or binary, causes a computer "to perform indicated tasks according to encoded instructions", as opposed to a data fil ...

form only. Multiple copy use is allowed. Participants receive up to 20 hours of staff assistance.

Single-Use Participants

Single-use participants are restricted to use RELAP5-3D on a single computer, one user at a time. They receive the RELAP5-3D executable code and may receive up to 5 hours of staff assistance.

University Participants

University Participants may acquire a license to RELAP5-3D for educational purposes.

Training Participants

Training participants have two main options available: they can receive a 3-month single-use license for the RELAP5-3D code and up to 10 hours of staff assistance, or a 3-month multiple-use license and up to 40 hours of on-call technical assistance. Alternative arrangements can be made based on customers' needs. These levels of participation are designed for those interested in participating in training courses. One set of RELAP5-3D training videos is included.

Major RELAP5-3D Releases

Notes

References

*J. A. Findley and G. L. Sozzi, "BWR Refill-Reflood Program – Model Qualification Task Plan," EPRI NP-1527, NUREG/CR-1899, GEAP-24898, October 1981. *T. M. Anklam, R. J. Miller, M. D. White, "Experimental Investigation of Uncovered-Bundle Heat Transfer and Two-Phase Mixture Level Swell Under High-Pressure and Low Heat Flux Conditions," NUREG/CR-2456, ORNL-5848, Oak Ridge National Laboratory, March 1982. *K. Carlson, R. Riemke, R. Wagner, J. Trapp, "Addition of Three-Dimensional Modeling," RELAP5/TRAC-B International Users Seminar, Baton Rouge, LA, November 4–8, 1991. *R. Riemke, "RELAP5 Multi-Dimensional Constitutive Models," RELAP5/TRAC-B International Users Seminar, Baton Rouge, LA, November 4–8, 1991. *H. Finnemann and A. Galati, "NEACRP 3-D LWR Core Transient Benchmark – Final Specifications," NEACRP-L-335 (Revision 1), January, 1992. *K. Carlson, R. Riemke, R. Wagner, "Theory and Input Requirements for the Multi-Dimensional Component in RELAP5 for Savannah River Site Thermal-Hydraulic Analysis," EGG-EAST-9878, Idaho National Engineering Laboratory, July, 1992. *K. Carlson, C. Chou, C. Davis, R. Martin, R. Riemke, R. Wagner, "Developmental Assessment of the Multi-Dimensional Component in RELAP5 for Savannah River Site Thermal-Hydraulic Analysis," EGG-EAST-9803, Idaho National Engineering Laboratory, July, 1992. *K. Carlson, C. Chou, C. Davis, R. Martin, R. Riemke, R. Wagner, R. Dimenna, G. Taylor, V. Ransom, J. Trapp, "Assessment of the Multi-Dimensional Component in RELAP5/MOD2.5", Proceedings of the 5th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Salt Lake City, Utah, USA, September 21–24, 1992. *P. Murray, R. Dimenna, C. Davis, "A Numerical Study of the Three Dimensional Hydrodynamic Component in RELAP5/MOD3", RELAP5 International Users Seminar, Boston, MA, USA, July, 1993. *G. Johnsen, "Status and Details of the 3-D Fluid Modeling of RELAP5," Code Application and Maintenance Program Meeting, Santa Fe, NM, October, 1993. *H. Finnemann, et al., "Results of LWR Core Transient Benchmarks," Proceedings of the Joint International Conference on Mathematical Methods and Supercomputing in Nuclear Applications, Vol. 2, pg. 243, Kernforschungszentrum, Karlsruhe, Germany, April, 1993. *A. S. Shieh, V. H. Ransom, R Krishnamurthy, RELAP5/MOD3 Code Manual Volume 6: Validation of Numerical Techniques in RELAP5/MOD3, NUREG/CR-5535, EGG-2596, October, 1994. *C. Davis, "Assessment of the RELAP5 Multi-Dimensional Component Model Using Data from LOFT Test L2-5," INEEL-EXT-97-01325, Idaho National Engineering Laboratory, January, 1998. *R. M. Al-Chalabi, et al., "NESTLE: A Nodal Kinetics Code," Transactions of the American Nuclear Society, Volume 68, June, 1993. *J. L. Judd, W. L. Weaver, T. Downar, J. G. Joo, "A Three Dimensional Nodal Neutron Kinetics Capability for RELAP5," Proceedings of the 1994 Topical Meeting on Advances in Reactor Physics, Knoxville, TN, April 11–15, 1994, Vol. II, pp 269–280. *E. Tomlinson, T. Rens, R. Coffield, "Evaluation of the RELAP5/MOD3 Multidimensional Component Model", RELAP5 International Users Seminar, Baltimore, MD, August 29 – September 1, 1994. *K. Carlson, "1D to 3D Connection for the Semi-Implicit Scheme," R5M3BET-001, Idaho National Engineering Laboratory, June, 1997. *A. Shieh, "1D to 3D Connection for the Nearly-Implicit Scheme," R5M3BET-002, Idaho National Engineering Laboratory, June, 1997. *J. A. Galbraith, G. L. Mesina, "RELAP5/RGUI Architectural Framework", Proceedings of the 8th International Conference on Nuclear Energy (ICONE-8), Baltimore, MD, USA, April 2–6, 2000. *G. L. Mesina and P. P. Cebull, "Extreme Vectorization in RELAP5-3D," Proceedings of the Cray User Group 2004, Knoxville, TN, USA, May 16–21, 2004. *D. P. Guillen, G. L. Mesina, J. M. Hykes, "Restructuring RELAP5-3D for Next Generation Nuclear Plant Analysis," 2006 Transactions of the American Nuclear Society, Vol. 94, June 2006. *G. L. Mesina, "Reformulation RELAP5-3D in FORTRAN 95 and Results," Proceedings of the ASME 2010 Joint US-European Fluids Engineering Summer Meeting and 8th International Conference on Nanochannels Microchannels, and Minichannels, FEDSM2010-ICNMM2010, Montreal, Quebec, Canada, Aug 1-5, 2010. *The RELAP5-3D Code Development Team, RELAP5-3D Code Manual Volume I: Code Structure, System Models and Solution Methods, INL-EXT-98-00834-V1, Revision 4.2, Idaho National Laboratory, June, 2014. *The RELAP5-3D Code Development Team, RELAP5-3D Code Manual Volume II: User’s Guide and Input Requirements, INEEL-EXT-98-00834, Revision 4.2, Section 8.7, Idaho National Laboratory, PO Box 1625, Idaho Falls, Idaho 83415, June, 2014. *The RELAP5-3D Code Development Team, RELAP5-3D Code Manual Volume II: User’s Guide and Input Requirements, Appendix A, INEEL-EXT-98-00834, Revision 4.2, Idaho National Laboratory, PO Box 1625, Idaho Falls, Idaho 83415, June, 2014. *The RELAP5-3D Code Development Team, RELAP5-3D Code Manual Volume III: Developmental Assessment, INL-EXT-98-00834, Revision 4.2, June, 2014. *The RELAP5-3D Code Development Team, RELAP5-3D Code Manual Volume IV: Models and Correlations, INL-EXT-98-00834, Revision 4.2, June, 2014. *The RELAP5-3D Code Development Team, RELAP5-3D Code Manual Volume V: User's Guidelines, INL-EXT-98-00834, Revision 4.2, June, 2014. *G. L. Mesina, D. L. Aumiller, F. X. Buschman, "Automated, Highly Accurate Verification of RELAP5-3D," ICONE22-31153, Proceedings of the 22nd International Conference on Nuclear Engineering, Prague, Czech Republic, July 7–11, 2014.

External links

RELAP5-3D HomepageInternational RELAP5 Users Group
{{DEFAULTSORT:RELAP5-3D Fortran software Physics software Industrial software Computational fluid dynamics Nuclear reactors Idaho National Laboratory