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Keywords: Thermal-Hydraulics
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Proceedings Papers

Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A101, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92642
..., China ABSTRACT The multiple-physics modeling has been demonstrated to be a high-fidelity and effective method for the analysis of reactor core physics and thermal-hydraulics. OpenMC is a communitydeveloped Monte Carlo neutron and photon transport simulation code. CTF is a subchannel thermal-hydraulics...
Proceedings Papers

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A022, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64703
... advantages are Keywords: Thermal-hydraulics, system code, solar salt, its thermal stability, large temperature range, low cost, high MMR, V & V density, and low vapor pressure. For example, MMR is a prismatic block design which has emerged as one preferred 1. INTRODUCTION concept of gas cooled reactors (GCRs...
Proceedings Papers

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, V001T01A013, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16599
... to eventually diminish with increasingly lower hold points, indicating a reduction in retained water. Keywords: dry cask storage, vacuum drying, residual water, water retention, dew point, thermal-hydraulics NOMENCLATURE DAQ data acquisition system DP dew point MS mass spectrometer NPT national pipe thread PV...
Proceedings Papers

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A040, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16741
... helical coiled tube LBE fast reactor modeling thermal-hydraulics Abstract Lead and Bismuth Eutectic (LBE) cooled fast reactor is attracting attention due to its advantages in safety. A thermal hydraulic analysis model is developed for an LBE cooled fast reactor helical coiled type...
Proceedings Papers

Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T11A003, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16196
... information in each calculation step. The validation result using FNCC provides good agreement with a result of the one-column flow distribution experiment. thermal-hydraulics high temperature gas-cooled reactor DEVELOPMENT OF A FLOW NETWORK CALCULATION CODE (FNCC) FOR HIGH TEMPERATURE GAS-COOLED...
Proceedings Papers

Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T11A004, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16199
...METHODOLOGY DEVELOPMENT FOR TRANSIENT FLOW DISTRIBUTION ANALYSIS IN HIGH TEMPERATURE GAS-COOLED REACTOR Takeshi Aoki 1, Hiroyuki Sato, Hirofumi Ohashi 1Japan Atomic Energy Agency Oarai, Japan ABSTRACT In the thermal hydraulic design of the prismatic-type of the high temperature gas cooled reactor...
Proceedings Papers

Proc. ASME. ICONE21, Volume 4: Thermal Hydraulics, V004T09A103, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16570
... uncertainty analysis for complex computational codes (e.g., RELAP5 thermal-hydraulics) computations. Different sampling techniques, dependencies between uncertainty sources, and accurate inference on results are among the issues to be considered. The dynamic behavior of the system codes executed in each time...
Proceedings Papers

Proc. ASME. ICONE21, Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes, V003T06A037, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16165
... methods comparing with other domestic PWR NPPs in China. Calculations and analyses were made to give thermal hydraulics support to Level-1 PSA of this VVER type PWR on the anticipated transient without scram (ATWS) accidents. The calculation of loss of main feed water ATWS was carried out using the RELAP5...
Proceedings Papers

Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 439-447, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54871
... in comparison to available post-accident data and measurements. The calculation captures the plant response in terms of the thermal-hydraulics very well during the first two phases. However, during the reflooding of the degraded core some discrepancies between the calculation and TMI-2 data are identified...
Proceedings Papers

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 4, Parts A and B, 401-413, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29386
... objective is to provide unique experimental data that are needed for the validation of thermal- hydraulic codes and to support safety assessments for VVER- 1000 reactors. Under OECD PSB-VVER project, five experiments were to be performed. Performance of each experiment in PSB-VVER was preceded by design...
Proceedings Papers

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 4, Parts A and B, 893-903, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29933
... 1 Copyright © 2010 by ASME Proceedings of the 18th International Conference on Nuclear Engineering ICONE18 May 17-21, 2010, Xi an, China ICONE18-29933 VALIDATION OF CATHARE V2.5 THERMAL-HYDRAULIC CODE AGAINST FULL-SCALE PERSEO TESTS FOR DECAY HEAT REMOVAL IN LWRS Giacomino Bandini ENEA Centro...
Proceedings Papers

Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 3, 95-103, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22098
... Reactor Severe Accident Thermal-Hydraulics In-Vessel Debris Cooling 10 G FO A, fet ta- as en annu the r evalu Some gap fluxes There deve restri and avera patte fluxes We e simpl perfo Institu Proceedings of ICONE10 10th International Conference on Nuclear Engineering 2 ME - 1 - lar gap...
Proceedings Papers

Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 69-81, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22350
... As the result of the advancing TCP/IP based inter-process communication technology, more and more legacy thermal-hydraulic codes have been coupled with neutronics codes to provide best-estimate capabilities for reactivity related reactor transient analysis. Most of the coupling schemes are based...
Topics: Cycles
Proceedings Papers

Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 3, 795-801, April 25–29, 2004
Publisher: American Society of Mechanical Engineers
Paper No: ICONE12-49496
... R&D project to investigate thermal-hydraulic performance in tight-lattice rod bundles for Reduced-Moderation Water Reactor (RMWR) is started at Japan Atomic Energy Research Institute (JAERI) in collaboration with power company, reactor vendors, universities since 2002. The RMWR can attain...
Topics: Fuel rods, Water