1-20 of 24
Keywords: RELAP5
Close
Follow your search
Access your saved searches in your account

Would you like to receive an alert when new items match your search?
Close Modal
Sort by
Proceedings Papers

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A064, August 8–12, 2022
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 5: Nuclear Safety, Security, and Cyber Security, V005T05A022, August 8–12, 2022
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
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
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
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
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 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A047, August 8–12, 2022
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

Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A037, August 8–12, 2022
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
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. 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
Paper No: ICONE28-64466
..., the RELAP5 4.0 code is used to model the system, and then the numerical calculation of steady and transient state was M Mass (kg) carried out to obtain the important thermal-hydraulic P Pressure (Pa) characteristic parameters. Meanwhile, the variations of the parameters were obtained during the transient...
Proceedings Papers

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A009, August 4–6, 2021
Paper No: ICONE28-64117
... Proceedings of the 2021 28th International Conference on Nuclear Engineering ICONE28 August 4-6, 2021, Virtual, Online ICONE28-64117 RELAP5 CODE ANALYSES OF PKL-4 PROJECT TEST ON PWR MULTIPLE STEAM GENERATOR TUBE RUPTURE ACCIDENT WITH RECOVERY ACTIONS SEKINE Masashi 1, KANEKO Junichi 1, and TAKEDA...
Proceedings Papers

Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A093, August 4–6, 2021
Paper No: ICONE28-66240
... influence the two-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...
Proceedings Papers

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A019, August 4–5, 2020
Paper No: ICONE2020-16294
..., a reasonable power-up 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...
Proceedings Papers

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A020, August 4–5, 2020
Paper No: ICONE2020-16296
...Abstract 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...
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
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 3, 635-640, May 17–21, 2010
Paper No: ICONE18-29900
... 08 04 2011 The RELAP5/SCDAP Mod3.2(am5) code is employed to simulate the OSU-AP1000-05 test conducted in the A dvanced P lant Ex perimental (APEX) test facility at Oregon State University (OSU). The APEX-1000 test facility is an one-fourth height, one-half time scale, and reduced...
Proceedings Papers

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 2, 425-430, May 17–21, 2010
Paper No: ICONE18-30215
... for novice users, the development of representative sample problems and graphics displays, and the type of training provided to support the users. A case study is presented in the paper outlining the sample problems and displays for use in novice RELAP5 and RELAP/SCDAPSIM user training classes. RELAP...
Proceedings Papers

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 4, Parts A and B, 243-248, May 17–21, 2010
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...
Proceedings Papers

Proc. ASME. ICONE16, Volume 3: Thermal Hydraulics; Instrumentation and Controls, 579-588, May 11–15, 2008
Paper No: ICONE16-48578
... 09 07 2009 In order to develop a thermal-hydraulic analysis model of the SG (steam-generator) to simulate transient phenomena in the FBR (sodium cooled fast breeder reactor) MONJU, JNES (Japan Nuclear Energy Safety Organization) validated a SG analysis model using the RELAP5/3D code...
Proceedings Papers

Proc. ASME. ICONE16, Volume 3: Thermal Hydraulics; Instrumentation and Controls, 759-768, May 11–15, 2008
Paper No: ICONE16-48720
... circuits heat removal capability. A quite detailed model of the EFIT reactor has been developed for the RELAP5 thermal-hydraulic code to be used in preliminary accidental transient analyses aimed at verifying the validity of the adopted solutions for the current reactor design with respect to the safety...