THACT-RR, Analysis of Thermal Hydraulics Transients in Research Reactor Core
Creators
- 1. Centre de Radioprotection de et Surete (C.R.S.), 2 Boulevard F. Fanon, BP 1017 Alger Gare, Alger 16000 (Algeria)
- 2. Centre de Developpement des Systems Energetiques (C.D.S.E.), BP 180 Ain-Oussera, 17200 Djelfa (Algeria)
Description
1 - Description of program or function: A Computer Program for Analyzing Thermal-Hydraulics transients in Research Reactors. THACT-RR is a channel code. It analyses the transient response of a research reactor core after power excursions or coolant flow and/or coolant temperature changes. The THACT-RR code provides a homogeneous one-dimensional compressible fluid flow capability with an optional voiding model that estimates the void produced by sub-cooled boiling. It allows flow reversal and sub-cooled nucleate boiling. It also includes a selection of flow instability, departure from nucleate boiling, single and two-phase heat transfer correlations, and a physical properties library adapted to pressures, temperatures, and flow rates encountered in research reactors. 2 - Method of solution: The conservation laws are solved by the method of Characteristics coupled with an implicit finite difference technique to insure stability and convergence of the numerical scheme. The conduction equation is solved by an implicit finite difference method. 3 - Restrictions on the complexity of the problem: The code is not adapted to very fast transient problems.
Additional details
Identifiers
Publishing Information
- Imprint Pagination
- [html]
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 39105829
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Computer Program Description, Non-conventional Literature
- Descriptors DEI
- COMPUTER PROGRAM DOCUMENTATION; COMPUTERIZED SIMULATION; CONSERVATION LAWS; COOLANTS; EXCURSIONS; FINITE DIFFERENCE METHOD; FLOW RATE; FLUID FLOW; HEAT TRANSFER; NUCLEATE BOILING; ONE-DIMENSIONAL CALCULATIONS; REACTOR ACCIDENT SIMULATION; REACTOR CORES; RESEARCH REACTORS; T CODES; THERMAL HYDRAULICS; TRANSIENTS; WEBSITES
- Descriptors DEC
- ACCIDENTS; BOILING; CALCULATION METHODS; COMPUTER CODES; DOCUMENT TYPES; ENERGY TRANSFER; FLUID MECHANICS; HYDRAULICS; ITERATIVE METHODS; MATHEMATICAL SOLUTIONS; MECHANICS; NUMERICAL SOLUTION; PHASE TRANSFORMATIONS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SIMULATION
Optional Information
- Notes
- 9 refs.