Development and validation of transient analysis module in nodal diffusion code RAST-V with Kalinin-3 coolant transient benchmark
0
조회
0
다운로드
0
인용
0
참고문헌
키워드
초록
This study introduces a transient analysis module developed for RAST-V and validates it using the Kalinin-3 benchmark problem. For the benchmark analysis, RAST-V standalone and STREAM/RAST-V calculations were performed. STREAM supplies the few-group constants and RAST-V conducts a 3D core simulation utilizing fewgroup cross-sectional data. To improve accuracy, the main solver was developed based on the advanced semianalytic nodal method. To evaluate the computational capability of the transient analysis module in RAST-V, Kalinin-3 benchmark is employed. Kalinin-3 represents a coolant transient benchmark that offers experimental data during the deactivation of the Main Circulation Pumps. Consequently, the transient calculations reflected the changes in the reactor flow rate. Benchmark comprising steady-state and transient calculations. During the steady state, the STREAM/RAST-V combination demonstrated a 30 ppm root mean square difference from 0 to 128.50 EFPD. For the transient calculations, STREAM/RAST-V showed power differences within ±7 % over a range of 0–300 s. Axial offset differences were within ±3 %, and the RMS difference in radial power ranged within 2.596 % at both 0 and 300 s. Overall, this study effectively demonstrated the newly developed transient solver in RAST-V and validated it using the Kalinin-3 benchmark problem.
Abstract
This study introduces a transient analysis module developed for RAST-V and validates it using the Kalinin-3 benchmark problem. For the benchmark analysis, RAST-V standalone and STREAM/RAST-V calculations were performed. STREAM supplies the few-group constants and RAST-V conducts a 3D core simulation utilizing fewgroup cross-sectional data. To improve accuracy, the main solver was developed based on the advanced semianalytic nodal method. To evaluate the computational capability of the transient analysis module in RAST-V, Kalinin-3 benchmark is employed. Kalinin-3 represents a coolant transient benchmark that offers experimental data during the deactivation of the Main Circulation Pumps. Consequently, the transient calculations reflected the changes in the reactor flow rate. Benchmark comprising steady-state and transient calculations. During the steady state, the STREAM/RAST-V combination demonstrated a 30 ppm root mean square difference from 0 to 128.50 EFPD. For the transient calculations, STREAM/RAST-V showed power differences within ±7 % over a range of 0–300 s. Axial offset differences were within ±3 %, and the RMS difference in radial power ranged within 2.596 % at both 0 and 300 s. Overall, this study effectively demonstrated the newly developed transient solver in RAST-V and validated it using the Kalinin-3 benchmark problem.
참고문헌 (28)
- J. Jang, "Development of Nodal Diffusion Code for VVER and HTGR Analysis with Advanced Semi Analytic Nodal Method", Doctor, pp.2023
- J. Jang, "Development of nodal diffusion code RAST-V for Vodo–Vodyanoi Energetichesky reactor analysis", Nucl. Eng. Technol, 54, pp.3494~3515 (2022)[DOI]
- J. Jang, "Analysis of Rostov-II benchmark using conventional two-step code systems", Energies, 15, pp.3318~ (2022)[DOI]
- "KALININ-3 coolant transient benchmark"[URL]
- Description of a Transient Caused by the Switching-Off of One of the Four Operating MCP at Nominal Reactor Power at NPP Kalinin Unit 3, vol. 2009, "V. A. Tereshonok", National Environment Agency – Singapore, DOC, pp.2009, 6~
- "Arcadia Revision Rod Ejection Accident, Topical Report, ANP-10338NP, Zeroth Revision" (2015)[URL]
- S. H¨akkinen, "Validation of the Serpent 2-HEXTRANSMABRE code sequence in a VVER-1000 coolant transient", J. Nucl. Sci. Technol, 57, pp.1167~1180 (2020)[DOI]
- ATHLET, "KIKO3D Results of the OECD", NEA Benchmark for Coupled Codes on KALININ-3 NPP Measured Data, NENE, pp.2014, ~
- Y. Perin, "OECD KALININ-3 Benchmark: Neutronic Calculations of Exercises 3a and 3 with PARCS", 4th Workshop of OECD Kalinin-3 Benchmark (2013)
- A. Keresztúri, "Simulation of the OECD NEA Kalinin-3Benchmark (Phase 2) by the ATHLET-Kiko3d Code System", Fifth Workshop of OECD Kalinin-3 Benchmark (2013)
- a K. Emiliya Georgie, "Status of PSU", REL Benchmark Cross Section Library, 2013, ~
- C. A. S. Ojinnaka, "Analysis of the Kalinin-3 coolant transient benchmark by SKETCH-N", SKAZKA code system, 2020, pp.147, ~
- T. Y. Downar, "PARCS NRC—v3.3.1 Volume I: Input Manual", RES, 2018
- G. Jeong, "A Study on Enhancement of Computational Efficiency for Transient Nodal Calculations", Nuclear Engineering, pp.2003
- Benchmark on Reactivity Compensation of Boron Dilution by Stepwise Insertion of Control Rod Cluster into the VVER-1000 Core, Version 1.5, "M. Avramova", OECD Nuclear Energy Agency, ~
- E. Jeong, "Verification and Validation for Transient Calculation of STREAM", RAST-K 2.0, Ulsan National Institute of Science and Technology, 2018
- A. Keresztúri, "AER Benchmark Specification Sheet AER-DYN-001, AER Benchmark Book", Forschungszentrum Rossendorf, Institute of Safety Research, ~ (1999)
- AER Benchmark Specification Sheet AER-DYN-002, AER Benchmark Book, "U. Grundmann", Forschungszentrum Rossendorf, Institute of Safety Research, ~ (1999)
- K. Obaidurrahman, "Development and validation of coupled dynamics code"trikin"for VVER reactors", Nucl. Eng. Technol, 42, pp.259~270 (2010)[DOI]
- A. Carreno, "Adaptive time-step control for modal methods to integrate the neutron diffusion equation", Nucl. Eng. Technol, 53, pp.399~413 (2021)[DOI]
- S. Akbas, "Survey of Coupling Schemes in Traditional Coupled Neutronics and Thermal-Hydraulics Codes", IMECE2015 (2015)
- "Three-dimensional Reactor Dynamics Code for VVER Type Nuclear Reactors" (1995)[URL]
- P. Balestra, "Simulation of AER-DYN-002 and AERDYN-003 control rod ejection benchmarks by RELAP5-3D", PHISICS coupled codes, 2016, pp.193, 175~182
- J. Jang, "Verification of RAST-K Hexagonal Analysis Module with SNR and VVER-440 Benchmarks (online)", KNS Winter Meeting (2020)
- Y. Jo, "Analysis of simplified BWR full core with serpent-2", simulate-3 hybrid stochastic, Ann. Nucl. Energy, pp.2018, 111[DOI]
- M. Hursin, "BWR FULL CORE ANALYSIS with SERPENT", SIMULATE-3 HYBRID STOCHASTIC, Joint International Conference Mathematics and Computation, Supercomputing in Nuclear Applications and the Monte Carlo Method, pp.2015[DOI]
- Preoperational inspection report of Shin-Kori nuclear power plant Unit 3 (Initial Fuel Load and Startup Test, Vol. 2), , Korea Institute of Nuclear Safety, ~, pp.Kins (2016), AR-1008
- "OECD/NEA Multi-Physics Benchmarks for Traditional and Novel Coupled Codes, Workshop on Multiphysics Model Validation" (2017)[URL]