PARCS: Purdue advanced reactor core simulator
Creators
- 1. Purdue University, School of Nuclear Engineering, 1290 Nuclear Engineering Building, West Lafayette, Indiana 47907-1290 (United States)
- 2. Information Systems Laboratories (ISL), Idaho Falls, Idaho (United States)
- 3. Korea Atomic Energy Research Institute - KAERI, Taejon (Korea, Republic of)
- 4. U.S. Nuclear Regulator Comission, Rockville, Maryland (United States)
Description
PARCS is a three-dimensional reactor core simulator that solves the steady-state and time-dependent neutron diffusion or SP3 transport equations to predict the dynamic response of the reactor to reactivity perturbations such as control rod movements, boron concentration or changes in the temperature/fluid conditions in the reactor core. The code is applicable to both PWR and BWR cores loaded with either rectangular or hexagonal fuel assemblies. Multigroup diffusion or a SP3 kernel can be used for the rectangular geometry option. The multigroup diffusion kernel is used for the hexagonal geometry option. Currently under development is a multigroup SP3 capability method for cylindrical geometry. The PARCS code was chosen by the U.S. Nuclear Regulatory Commission (NRC) as its best estimate core neutronics code, and PARCS is coupled directly to the U.S. NRC thermal-hydraulics systems codes TRAC-M and RELAP5 using a message passing interface. The thermal-hydraulic solution is incorporated into PARCS as feedback into the few group cross sections. A depletion capability has also recently been added to PARCS that includes cross section interface capability to lattice physics codes such as HELIOS. The major features in PARCS include the ability to perform eigenvalue calculations, a transient (kinetics) calculation including decay heat and xenon and samarium treatment, the adjoint calculation and the depletion calculation. The primary use of PARCS involves a 3D calculation model for the realistic representation of the physical reactor. Numerous sophisticated spatial kinetics calculation methods have been incorporated into PARCS in order to accomplish the various tasks with high accuracy and efficiency
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park, IL (United States)
- Imprint Pagination
- 7 p.
Conference
- Title
- International Conference on the New Frontiers of Nuclear Technology: Reactor Physics, Safety and High-Performance Computing
- Acronym
- Physor 2002
- Dates
- 7-10 Oct 2002
- Place
- Seoul (Korea, Republic of)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 55004401
- Subject category
- S97: MATHEMATICAL METHODS AND COMPUTING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CALCULATION METHODS; CROSS SECTIONS; CYLINDRICAL CONFIGURATION; FUEL ASSEMBLIES; GEOMETRY; MATHEMATICAL SOLUTIONS; NEUTRON DIFFUSION EQUATION; PERTURBATION THEORY; PWR TYPE REACTORS; REACTIVITY; REACTOR CORES; REACTOR SIMULATORS; THERMAL HYDRAULICS; THREE-DIMENSIONAL CALCULATIONS; THREE-DIMENSIONAL LATTICES; TIME DEPENDENCE; TRANSPORT THEORY
- Descriptors DEC
- ANALOG SYSTEMS; CONFIGURATION; CRYSTAL LATTICES; CRYSTAL STRUCTURE; DIFFERENTIAL EQUATIONS; DIFFUSION EQUATIONS; ENRICHED URANIUM REACTORS; EQUATIONS; FLUID MECHANICS; FUNCTIONAL MODELS; HYDRAULICS; MATHEMATICS; MECHANICS; PARTIAL DIFFERENTIAL EQUATIONS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SIMULATORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 17 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)