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Frac Plug Forensics: Post-Fracture Plug Failure Root Cause Analysis and the Subsequent Impact on Stimulation Performance

PROCEEDINGS ARTICLE published 12 March 2024 in Day 2 Wed, March 20, 2024

Authors: Trent Pehlke | Greer Simpson | Tamara Maxwell | Chris McCann | Charles Bourgeois | Joshua Stibbs

Flowback Three-Phase Flowmeter Implementation for Post-Fracturing Cleanouts: A Case Study from Argentina

PROCEEDINGS ARTICLE published 12 March 2024 in Day 2 Wed, March 20, 2024

Authors: J. M. Mirande | J. Vassallo | P. Mambriani | C. Gonzalez | E. Fajardo | M. Vecchietti | R. Krasuk | A. Misonischnik

Exploration of Fuel Property Impacts on the Combustion of Late Post Injections Using Binary Blends and High-Reactivity Ether Bioblendstocks

PROCEEDINGS ARTICLE published 20 April 2023 in SAE WCX 2023, 04/18-04/20, 2023. Detroit, MI, USA

Authors: Srinath Subramanian | David Rothamer

Mary Sylvain, Décoloniser les Antilles ? Une histoire de l’État post-colonial (1946-1982) , Paris, Sorbonne Université Presses, 2021, 410 p., 28 €

JOURNAL ARTICLE published 9 March 2023 in 20 & 21. Revue d'histoire

Authors: Edenz Maurice

Utilization of Innovative Resin-Cement Blend to Enhance Wellbore Integrity

PROCEEDINGS ARTICLE published 7 March 2023 in Day 2 Mon, February 20, 2023

Authors: Wajid Ali | Faisal Abdullah Al-Turki | Athman Abbas | Abdullah Saleh Al-Yami | Vikrant Wagle | Ali Al-Safran

Full-Core Computational Fluid Dynamics Simulations Using NekRS

PROCEEDINGS ARTICLE published 2023 in 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20)

Authors: Dillon Shaver | Jun Fang | Haomin Yuan | Misun Min | Elia Merzari | Yu-Hsiang Lan

Construction of Campus Cainiao Post Station Service Quality Evaluation Model - Take Guangzhou College of Technology and Business as An Example

PROCEEDINGS ARTICLE published 2023 in Proceedings of the 4th International Conference on Economic Management and Model Engineering, ICEMME 2022, November 18-20, 2022, Nanjing, China

Authors: Lingzhi Zeng

Research on the Development of Core Professional Women in the Canadian Labor Market Based on Experimental Analysis

PROCEEDINGS ARTICLE published 2023 in Proceedings of the 4th International Conference on Economic Management and Model Engineering, ICEMME 2022, November 18-20, 2022, Nanjing, China

Authors: Gaoruisi Deng | Huaqiao Liu | Baoyi Wang

The SAIGA In-Pile Experimental Test to Study the Degradation of a SFR Core with Mitigation Devices in Severe Accident Conditions

PROCEEDINGS ARTICLE published 2023 in 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20)

Authors: F. Payot | F. Charollais | E. Dufour | Y. Lejeail | G. Blevin | L. Trotignon | G. Izarra | F. Michel | V. Dupont | N. Chikhi | R. Clavier | E. Batyrbekov | A. Vurim | A. Pakhnits | V. Baklanov

Comparison of CFD Simulations and Porous Media Simulations of a Gas-Cooled Pebble Bed Core Under Forced and Mixed Convection Conditions

PROCEEDINGS ARTICLE published 2023 in 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20)

Authors: Dezhi Dai | Prasad Vegendla | Haomin Yuan | Landon Brockmeyer | Adam Kraus | Adrian Tentner | David Reger

Modeling the Prismatic HTGR Core in SAM by Representative Channels

PROCEEDINGS ARTICLE published 2023 in 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20)

Authors: Taiyang Zhang | Thanh Hua | Zhiee Ooi | Ling Zou | Caleb Brooks

Implementation of a Three-Field Framework in TRACE to Improve the Prediction of Reactor Core Reflood Conditions Part I

PROCEEDINGS ARTICLE published 2023 in 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20)

Authors: Matthew Bernard | Stephen Bajorek

Transient Cooling Investigation of a Conceptual Core Catcher Design with Embedded Cooling Tubes Using a GOTHIC 3D Model

PROCEEDINGS ARTICLE published 2023 in 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20)

Authors: Zhuo Liu | Wei Li | Qiang Guo | Yidan Yuan | Ningxi Jia | Yu Jin | Weimin Ma

Comparison Between EDF MAAP5.04, EPRI MAAP5.06 and CATHARE Codes on Hypothetical Accidental Transients Leading to a Core Damage on the NUWARD SMR Design

PROCEEDINGS ARTICLE published 2023 in 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20)

Authors: Jeremy Bittan

Experimental Investigation of the Post-Dryout Heat Transfer with R-134a at High Pressures

PROCEEDINGS ARTICLE published 2023 in 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20)

Authors: N. Rensch | L. Köckert | D. Klingel | A. Badea | X. Cheng

Preliminary Study on Melt Spreadability in Ex-Vessel Core Catcher Under Dry Condition

PROCEEDINGS ARTICLE published 2023 in 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20)

Authors: Byung Kim | Dae Lee | Sun Yoon

Validation Practices of Multi-Physics Core Performance Analysis in an Advanced Reactor Design Study

PROCEEDINGS ARTICLE published 2023 in 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20)

Authors: Norihiro Doda | Shinya Kato | Erina Hamase | Kazuki Kuwagaki | Norihiro Kikuchi | Kazuya Ohgama | Kazuo Yoshimura | Ryuji Yoshikawa | Kenji Yokoyama | Tomoyuki Uwaba | Masaaki Tanaka

Optimization of Person-Post Matching Model for Improving Economic Management Ability

PROCEEDINGS ARTICLE published 2023 in Proceedings of the 4th International Conference on Economic Management and Model Engineering, ICEMME 2022, November 18-20, 2022, Nanjing, China

Authors: Yuhong Bai

Research on the Digital Development of Human Resource Management in Large Enterprises in the Post-epidemic Period

PROCEEDINGS ARTICLE published 2023 in Proceedings of the 4th International Conference on Economic Management and Model Engineering, ICEMME 2022, November 18-20, 2022, Nanjing, China

Authors: Xiaoqi Xu

Thermal Stress Analysis for Heat Pipe Cooled Microreactor Core Varying Condenser Temperature

PROCEEDINGS ARTICLE published 2023 in 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20)

Authors: Myung Jeong | San Lee | Jaeuk Im | Hyoung Cho