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Proceedings Papers

Validation of TRACE Simulation of Small-Break LOCA Test (SB-CL-18) in the Large-Scale Test Facility

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Hideki Yagihashi, Kaho Goto, Masashi Sekine, Naofumi Tsukamoto
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A036, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134596
https://doi.org/10.1115/ICONE31-134596
...-dimensional thermal hydraulics simulation code TRACE. To show the applicability of TRACE to small-break LOCA, the simulation of the SB-CL-18 was carried out using TRACE and the simulation results were compared with the measurements for several parameters. Furthermore, the loop seal clearing phenomenon...
View Paper titled, Validation of TRACE Simulation of Small-Break LOCA Test (SB-CL-18) in the Large-Scale Test Facility
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Topics: Loss of coolant accidents, Pressurized water reactors, Simulation, Test facilities
Proceedings Papers

Modeling Co-Current and Counter-Current Flow: A Performance Evaluation of the TRACE Condensation Model with Non-Condensable and Light Gases

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Samah A. Albdour, Yacine Addad, Imran Afgan
Proc. ASME. ICONE31, Volume 10: Risk Assessments and Management; Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V010T13A004, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134262
https://doi.org/10.1115/ICONE31-134262
... work utilizes a condensation setup in KAIST’s passive containment cooling system (PCCS) facility, chosen for its validation accessibility. Unlike prior validations focused on pure steam and air using RELAP5/MOD3.2, this study employs TRACE validation to explore the effects of non-condensable gases...
View Paper titled, Modeling Co-Current and Counter-Current Flow: A Performance Evaluation of the TRACE Condensation Model with Non-Condensable and Light Gases
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Topics: Condensation, Containment, Cooling systems, Flow (Dynamics), Gases, Heat transfer coefficients, Modeling, Performance evaluation
Proceedings Papers

Preliminary Transient Analysis for LBE-Cooled Fast Reactor BLESS-D

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Mian Xing, Linsen Li, Gang Zheng, Junlang Wen, Chunyuan Liu, Yeoh Eing Yee, Zhen Luo, Peidong Sun, Jinjun Feng
Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T04A002, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-63220
https://doi.org/10.1115/ICONE28-63220
... and secondary boundary of BLESS-D is modeled with SNAP/TRACE. And the steady state simulation results are compared with the design values which shows good agreement. After that, the transient accidents under different conditions are studied to evaluate the feasibility and safety of the current design...
View Paper titled, Preliminary Transient Analysis for LBE-Cooled Fast Reactor BLESS-D
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Topics: Fast neutron reactors, Safety, Transient analysis, Transients (Dynamics), Design, Reactor vessels, Accidents, Boilers, Conceptual design, Coolants
Proceedings Papers

Heat Transfer for Supercritical Flow With TRACE

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Jay Spore, Glenn Roth
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T02A004, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16753
https://doi.org/10.1115/ICONE2020-16753
... to be included into TRACE. HEAT TRANSFER FOR SUPERCRITICAL FLOW WITH TRACE Jay Spore and Glenn Roth1 Information Systems Laboratories Idaho Falls, ID ABSTRACT Flow regimes at water pressures above the critical pressure are characterized as supercritical flow. Supercritical flows have no phase change. The heat...
View Paper titled, Heat Transfer for Supercritical Flow With TRACE
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Topics: Flow (Dynamics), Heat transfer, Pressure
Proceedings Papers

Validation of TRACE Code Against ROSA/LSTF Test for SBLOCA of Pressure Vessel Upper-Head Small Break

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Mian Xing, Xiao Hu, Yaodong Chen, Liangxing Li, Weimin Ma
Proc. ASME. ICONE21, Volume 4: Thermal Hydraulics, V004T09A042, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15548
https://doi.org/10.1115/ICONE21-15548
... 1 Copyright © 2013 by ASME VALIDATION OF TRACE CODE AGAINST ROSA/LSTF TEST FOR SBLOCA OF PRESSURE VESSEL UPPER-HEAD SMALL BREAK Mian Xing Division of Advanced Nuclear Energy Technology, State Nuclear Power Reseach Institute, SNPRI Beijing, China Xiao Hu State Nuclear Power Technology Corporation...
View Paper titled, Validation of TRACE Code Against ROSA/LSTF Test for SBLOCA of Pressure Vessel Upper-Head Small Break
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Topics: Pressure vessels, Flow (Dynamics), Pressurized water reactors, Accidents, Coolants, Modeling, Pressure, Safety, Temperature, Test facilities
Proceedings Papers

TRACE Validation Against LOCA Transients Performed on FIX-II Facility

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Xiao Hu, Mian Xing, Weimin Ma
Proc. ASME. ICONE21, Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes, V003T06A019, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15553
https://doi.org/10.1115/ICONE21-15553
... As a latest developed computational code, TRACE is expected to be useful and effective for analyzing the thermal-hydraulic behaviors in design, licensing and safety analysis of nuclear power plant. However, its validity and correctness have to be verified and qualified before its application...
View Paper titled, TRACE Validation Against LOCA Transients Performed on FIX-II Facility
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Topics: Safety, Transients (Dynamics)
Proceedings Papers

Modeling of Sodium Two-Phase Flow With the TRACE Code

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Aurelia Chenu, Konstantin Mikityuk, Rakesh Chawla
Proc. ASME. ICONE17, Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems, 803-811, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75131
https://doi.org/10.1115/ICONE17-75131
... 23 02 2010 In the framework of PSI’s FAST code system, the TRACE thermal-hydraulics code is being extended for representation of sodium two-phase flow. As the currently available version (v.5) is limited to the simulation of only single-phase sodium flow, its applicability range...
View Paper titled, Modeling of Sodium Two-Phase Flow With the TRACE Code
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Topics: Modeling, Sodium, Sodium fast reactors, Two-phase flow