Advanced training simulator models. Implementation and validation
- 1. Studsvik Scandpower, Inc., Idaho Falls, ID (United States)
- 2. Thunder Simulation, Inc., St. Marys, GA (United States)
Description
Modern training simulators are required to replicate plant data for both thermal-hydraulic and neutronic response. Replication is required such that reactivity manipulation on the simulator properly trains the operator for reactivity manipulation at the plant. This paper discusses advanced models which perform this function in real-time using the coupled code system THOR/S3R. This code system models the all fluids systems in detail using an advanced, two-phase thermal-hydraulic a model. The nuclear core is modeled using an advanced, three-dimensional nodal method and also by using cycle-specific nuclear data. These models are configured to run interactively from a graphical instructor station or handware operation panels. The simulator models are theoretically rigorous and are expected to replicate the physics of the plant. However, to verify replication, the models must be independently assessed. Plant data is the preferred validation method, but plant data is often not available for many important training scenarios. In the absence of data, validation may be obtained by slower-than-real-time transient analysis. This analysis can be performed by coupling a safety analysis code and a core design code. Such a coupling exists between the codes RELAP5 and SIMULATE-3K (S3K). RELAP5/S3K is used to validate the real-time model for several postulated plant events. (author)
Additional details
Publishing Information
- Publisher
- Atomic Energy Society of Japan
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- The 16th pacific basin nuclear conference. Pacific partnership toward a sustainable nuclear future
- Imprint Pagination
- [2022 p.]
- Journal Page Range
- [6 p.]
Conference
- Title
- 16. pacific basin nuclear conference
- Acronym
- 16PBNC
- Dates
- 13-18 Oct 2008
- Place
- Aomori (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 41004389
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCHMARKS; IMPLEMENTATION; NODAL EXPANSION METHOD; R CODES; REACTOR CORES; REACTOR SIMULATORS; REAL TIME SYSTEMS; S CODES; SAFETY ANALYSIS; THERMAL HYDRAULICS; TRAINING; TRANSIENTS; TWO-PHASE FLOW; VALIDATION; VOIDS; WATER COOLED REACTORS
- Descriptors DEC
- ANALOG SYSTEMS; CALCULATION METHODS; COMPUTER CODES; EDUCATION; FLUID FLOW; FLUID MECHANICS; FUNCTIONAL MODELS; HYDRAULICS; MECHANICS; REACTOR COMPONENTS; REACTORS; SIMULATORS; TESTING
Optional Information
- Notes
- This CD-ROM can be used for WINDOWS 9x/NT/2000/ME/XP/VISTA, MACINTOSH; Acrobat Reader is included; Data in PDF format, Folder Name FullPaper, Paper ID P16P1001.pdf; 2 refs., 2 figs.