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1-20 of 28
Keywords: RELAP5
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Proceedings Papers
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A018, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-133151
... Technology, Tsinghua University, Beijing 100084, China 2. Institute of Nuclear Science and Engineering, North China Electric Power University, Beijing 102206, China ABSTRACT The RELAP5 code was employed to study the natural circulation characteristics and core thermal-hydraulic parameters of THFR (Tsinghua...
Topics:
Heat
Proceedings Papers
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A063, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135143
... Containment Cooling System (PCS), etc. These systems and equipment work together to achieve passive emergency core cooling function. In this paper, a RELAP5 model is establish to analyze a small LOCA accident sequence. Simulations are conducted for five stages after the accident, including natural circulation...
Proceedings Papers
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A017, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-132735
..., thus have more advantages in reduced-order modeling. While the applications of these methods are rarely involving the OTSG. This paper aims to analyze the applicability of DMD and POD for OTSG reduced order modelling. The simulation data of main parameters calculated via RELAP5 are collected...
Proceedings Papers
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A008, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-131657
... Abstract RELAP5 has some shortcomings in calculating the submerged cooling process of rectangular channels, especially in the post critical heat transfer model. Based on the experimental data of submerged cooling in rectangular channel, the droplet flow precursor cooling heat transfer model...
Proceedings Papers
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A037, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91004
...-of-coolant accident (LOCA). This paper designs and analyses a set of mitigation measures for LOCA in the high flux research reactor. Relap5 is used for thermal hydraulic system analysis and breaks at three different sites are simulated. The primary coolant system includes four loops, each of which consists...
Proceedings Papers
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A034, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90971
... of liquid phase and gas, and geometry of pipeline on flooding were also studied. LOCA hot leg countercurrent flow RELAP5 two-phase flow Proceedings of the 2022 29th International Conference on Nuclear Engineering ICONE29 August 8-12, 2022, Virtual, Online ICONE29-90971 COUNTERCURRENT FLOW...
Proceedings Papers
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A022, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91516
... estimate code (RELAP5) with a statistical tool (RAVEN). RELAP5 is used to simulate the thermal-hydraulic response under LOFW accident while a set of uncertainty parameters are propagated through the RELAP5 model using RAVEN. These distributions were sampled using a Latin Hypercube Sampling (LHS) technique...
Proceedings Papers
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A024, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90285
... in the deterioration of PRHR capacity. A RELAP5 system model and a CFD model were developed for the PRHR system of NHR-200-II, in both models, we focused on the prediction of thermal stratification phenomena in the ring headers of PRHR. Both the case of normal PRHR scenarios (i.e. the SG branches were successfully...
Proceedings Papers
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A039, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91486
... of the IHEL. The experimental results show that the IHEL provides adequate core cooling capacity. The RELAP5 code is evaluated by the experimental results. The sensitive calculations are conduct which the effects of several parameters include the primary side inlet temperature, the primary side mass flow rate...
Topics:
Heat
Proceedings Papers
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A026, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90343
... in the core section with peak power. The SLB safety analysis methodologies in Administration License Application for typical PWR in China are investigated in this paper. Based on the conservative universal methodology, the best-estimated code RELAP5/MOD3 is used to perform the SLB thermal-hydraulic...
Proceedings Papers
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A069, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92183
.... In the case of loss-of-flow accident happened in deep pool-type nuclear reactor, the natural circulation gradually established in pool to remove the residual heat after the flap valve opens. In this paper, a simulation model is developed based on the RELAP5 program. And the thermal-hydraulic behaviors...
Proceedings Papers
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A064, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92103
... Abstract To study the transient thermal-hydraulic characteristics of lead and lead-bismuth eutectic (LBE) in the reactor, Relap5 MOD3.2 was adapted to add the physical properties and liquid metal flow model of lead and lead bismuth through secondary development without changing its original...
Proceedings Papers
Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A047, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93387
... of the trend of flow, the temperature of the tube wall decreased rapidly and then increased slowly. Therefore, the results of various accident conditions in this investigation can contribute to the thermal fatigue analysis of IHX in the near future. intermediate heat exchanger RELAP5 sodium cooled fast...
Proceedings Papers
Wen Zhu, Qingche He, Luteng Zhang, Zaiyong Ma, Wan Sun, Wangtao Xu, Liangming Pan, Tao Huang, Shuhua Ding
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A093, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-66240
...-phase interface’s deformation, the distribution of the two phases, the flow pressure drop, etc. In this paper, the interfacial drag models in RELAP5 are assessed using GE mixture level swell experiments and FRIGG tests. GE Small Level Swell experiment and GE Large Level Swell experiment were...
Proceedings Papers
Conceptual Design and Evaluation of Residual Heat Removal System for Small Lead-Bismuth Fast Reactor
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, V001T04A012, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64466
... Abstract A high efficient and reliable residual heat removal system (RHRS), which is of great importance in the development of Lead-Bismuth Cooled Fast Reactor (LBFR), was conceptually designed in present study. Based on the design of the RHRS and LBFR, the RELAP5 4.0 code is used to model...
Proceedings Papers
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A009, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64117
..., a post-test analysis on the PKL test was carried out with RELAP5/MOD3.3 code (RELAP5). Although discrepancies from the test data appeared in some parameters, the code well predicted the overall trends of the major thermal-hydraulic responses observed in the PKL test. Case studies were also performed...
Proceedings Papers
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A019, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16294
... and power-down transient scheme is required to ensure operational stability when starting up and shutting down a reactor. RELAP5/MOD4.0 is a commercial software developed by Innovative System Software, LCC for transient analysis of light water reactors (LWR). After years of development and improvement...
Proceedings Papers
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A020, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16296
... Abstract This paper aims to validate the effectiveness of the widely used Relap5 code in simulating two-phase natural circulation, and its capability to predict flashing-induced instabilities. The RELAP5 code is validated against experimental data from the NMR test facility, which was designed...
Proceedings Papers
Proc. ASME. ICONE21, Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes, V003T06A013, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15314
... takes the form of directly safety injection, which has great effects on the flow and heat transfer of the reactor pressure vessel and it has influence on the process of the SBLOCA finally. In present work, an SBLOCA analytical model has been developed with RELAP5 code to analyze special design features...
Proceedings Papers
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 4, Parts A and B, 243-248, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29239
... 08 04 2011 On the basis of best estimate thermal-hydraulic system code RELAP5, sub-channel code COBRA-1V, and commercial Computational Fluid Dynamics (CFD) code CFX, a thermalhydraulic multi-scale coupled code RECOX has been developed. The coupling strategy was designed to keep...
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