Session: 13-01: Computer Code V&V - I
Paper Number: 134294
134294 - Validation and Verification of Asyst Code for Predicting Condensation Phenomena in Nuclear Reactor Safety Systems
Abstract:
The modeling of condensation phenomena in system codes presents formidable challenges due to phase-change processes' intricate and nonlinear nature. This paper delves into the assessment of the ASYST (Adaptive System Thermal-Hydraulic) code series, an advanced tool that amalgamates the functionalities of the SCDAPSIM and SAMPSON codes. With a focus on Best Estimate Plus Uncertainty (BEPU) simulation capabilities, this study evaluates ASYST's performance in predicting condensation events within a dedicated test facility at Khalifa University.
The test facility, designed for condensation studies, replicates a Passive Containment Cooling System (PCCS), a critical component of nuclear reactor safety systems. The validation and verification of the ASYST code against experimental data from this facility are crucial steps in gauging its accuracy and reliability in real-world scenarios.
The experimental setup comprises essential components such as a steam generator, storage water tank, test section, control panel, steam flow meter, heat exchanger, condensate tank, and an advanced data acquisition system. The steam generator, standing at a height of 0.5 meters, underscores its significance in the functionality of the experimental apparatus.
Validation efforts involve meticulously comparing ASYST simulations with experimental data to ensure alignment with real-system conditions. Simultaneously, the verification process confirms adherence to standards, captures physical phenomena and meets predefined quality and consistency criteria.
The condensation phase within the test facility serves as a benchmark for gauging ASYST's reliability and applicability in the context of nuclear reactor safety systems. This study contributes to the broader scientific understanding of condensation processes, shedding light on the dynamics involved. Moreover, it validates the efficacy of the ASYST code in thermal-hydraulic simulations.
The research enhances our understanding of condensation mechanisms, providing valuable insights into the potential real-world applications of the ASYST code. This study thoroughly tests ASYST's functionality in a controlled setting to determine how useful and trustworthy it is for checking passive safety systems in nuclear reactors.
This scientific study not only elucidates condensation mechanisms but also establishes the credibility of ASYST simulations through comprehensive validation and verification processes. The findings underscore the code's reliability, instilling confidence in its utilization for assessing passive safety systems in nuclear reactors. This research contributes significantly to advancing our knowledge of condensation processes. It reaffirms the ASYST code as a valuable tool in thermal-hydraulic simulations for nuclear reactor safety.
Keywords: ASYST code, Code validation and Verification, Condensation phenomena, Separate effect test facility
Highlights:
1. Post-test analysis of condensation separate effect test facility experimental campaign tests.
2. Thorough Validation and Verification of ASYST code for condensation phenomena.
Presenting Author: Yacine Addad KHALIFA UNIVERSITY
Presenting Author Biography: Dr. Yacine Addad holds the Associate Department Chair in Nuclear Engineering and Deputy Director of the Emirates Nuclear Technology Center (ENTC) within Khalifa University, UAE. He is an expert in the field of nuclear Thermal-Hydraulics (T-H) analysis. He is leading the Emirates Nuclear Technology Center (ENTC) Theme-1 research team focusing on the assessment of the thermal hydraulic safety analysis codes capabilities to mimic dominant T-H phenomena occurring in nuclear power plants under postulated accident scenarios including rare events.
Authors:
Satya Prakash Saraswat DEPARTMENT OF MECHANICLA AND NUCLEAR ENGINEERING, KHALIFA UNIVERSITY,ABUDHABI, UAEMubashir Hassan KHALIFA UNIVERSITY
Sameer Mohammad Osman Khalifa University Abu Dhabi, UAE
Chris Allison Innovative Systems Software (ISS) 3585 Briar Creek, Ammon
Yacine Addad KHALIFA UNIVERSITY
Validation and Verification of Asyst Code for Predicting Condensation Phenomena in Nuclear Reactor Safety Systems
Submission Type
Technical Paper Publication