Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovatio

Performance Study of the MORET Monte Carlo Code for Local Power Density Calculations in a Full Size Reactor Core

Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovatio ◽

10.1115/icone20-power2012-54535 ◽

2012 ◽

Cited By ~ 1

Author(s):

Franck Bernard ◽

Joachim Miss ◽

Gabriel Juhel

Keyword(s):

Monte Carlo ◽

Power Density ◽

Reactor Core ◽

Monte Carlo Code ◽

Local Power ◽

Performance Study ◽

Full Size

Download Full-text

Hydrogen Ingress Into Zirconium Alloys as a Life-Limiting Factor — Methods of In-Line Monitoring, Prediction and Control

Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovatio ◽

10.1115/icone20-power2012-54143 ◽

2012 ◽

Author(s):

M. B. Elmoselhi ◽

K. Tashiro ◽

A. C. Wallace

Keyword(s):

Zirconium Alloys ◽

Limiting Factor ◽

Prediction And Control ◽

And Control

Download Full-text

Building Maintenance Program for Piping and Pipe Support

Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovatio ◽

10.1115/icone20-power2012-55073 ◽

2012 ◽

Author(s):

Kotaro Iwahara ◽

Koji Yamamoto ◽

Satoshi Momiyama

Keyword(s):

Building Maintenance ◽

Maintenance Program

Download Full-text

Evaluation of Thermal Stress Distribution With Elasticoluminescent Materials

Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovatio ◽

10.1115/icone20-power2012-54360 ◽

2012 ◽

Author(s):

Wei Liu ◽

Taku Nagatake ◽

Kazuyuki Takase ◽

C. X. Wu ◽

Daisuke Ono ◽

...

Keyword(s):

Thermal Stress ◽

Stress Distribution ◽

Thermal Stress Distribution

Download Full-text

Standard Core Design and Safety Analysis for Advanced Power Reactor Plus (APR+)

Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovatio ◽

10.1115/icone20-power2012-54132 ◽

2012 ◽

Author(s):

Sang Jong Lee ◽

Yong Soo Park ◽

Jong Ryul Park

Keyword(s):

Power Reactor ◽

Safety Analysis

Download Full-text

A Study on the Public Perception in Nuclear Area in Brazil

Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovatio ◽

10.1115/icone20-power2012-54107 ◽

2012 ◽

Author(s):

Renata A. Almeida ◽

Maria de Lourdes Moreira ◽

Patricia Wieland ◽

Antonio Cesar F. Guimarães

Keyword(s):

Public Perception ◽

Nuclear Area ◽

The Public

Download Full-text

The Investigation of Thermal Neutron Scattering Data of Flibe

Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovatio ◽

10.1115/icone20-power2012-54939 ◽

2012 ◽

Author(s):

Longwei Mei ◽

Xiangzhou Cai ◽

Jingen Chen ◽

Wei Qin ◽

Wei Guo

Keyword(s):

Neutron Scattering ◽

Thermal Neutron ◽

Scattering Data ◽

Thermal Neutron Scattering

Download Full-text

Smart Energy Management and Comprehensive Utilization of Nuclear Energy

Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovatio ◽

10.1115/icone20-power2012-54389 ◽

2012 ◽

Author(s):

Shutang Zhu ◽

Zhaoqi Zhu

Keyword(s):

Energy Management ◽

Nuclear Energy ◽

Comprehensive Utilization ◽

Smart Energy Management

Download Full-text

Effect of Feeding Velocity on Wear Behavior of Graphite Ball Under Elevating Process With HTGR Fuel Handling System

Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovatio ◽

10.1115/icone20-power2012-54357 ◽

2012 ◽

Cited By ~ 1

Author(s):

Zhipeng Chen ◽

Xiaowei Luo ◽

Suyuan Yu

Keyword(s):

Wear Behavior ◽

Handling System ◽

Effect Of Feeding ◽

Htgr Fuel

Download Full-text

Resolution of the Pressure Locking Issue of Safety Related MOVs at NPP Krško

Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovatio ◽

10.1115/icone20-power2012-55003 ◽

2012 ◽

Author(s):

Tomislav Bajs ◽

Matija Balić ◽

Bogoljub Sember

Download Full-text

Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovatio
Latest Publications

TOTAL DOCUMENTS

H-INDEX

Published By ASME

Performance Study of the MORET Monte Carlo Code for Local Power Density Calculations in a Full Size Reactor Core

Hydrogen Ingress Into Zirconium Alloys as a Life-Limiting Factor — Methods of In-Line Monitoring, Prediction and Control

Building Maintenance Program for Piping and Pipe Support

Evaluation of Thermal Stress Distribution With Elasticoluminescent Materials

Standard Core Design and Safety Analysis for Advanced Power Reactor Plus (APR+)

A Study on the Public Perception in Nuclear Area in Brazil

The Investigation of Thermal Neutron Scattering Data of Flibe

Smart Energy Management and Comprehensive Utilization of Nuclear Energy

Effect of Feeding Velocity on Wear Behavior of Graphite Ball Under Elevating Process With HTGR Fuel Handling System

Resolution of the Pressure Locking Issue of Safety Related MOVs at NPP Krško

Export Citation Format

Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and InnovatioLatest Publications

TOTAL DOCUMENTS

H-INDEX

Published By ASME

Performance Study of the MORET Monte Carlo Code for Local Power Density Calculations in a Full Size Reactor Core

Hydrogen Ingress Into Zirconium Alloys as a Life-Limiting Factor — Methods of In-Line Monitoring, Prediction and Control

Building Maintenance Program for Piping and Pipe Support

Evaluation of Thermal Stress Distribution With Elasticoluminescent Materials

Standard Core Design and Safety Analysis for Advanced Power Reactor Plus (APR+)

A Study on the Public Perception in Nuclear Area in Brazil

The Investigation of Thermal Neutron Scattering Data of Flibe

Smart Energy Management and Comprehensive Utilization of Nuclear Energy

Effect of Feeding Velocity on Wear Behavior of Graphite Ball Under Elevating Process With HTGR Fuel Handling System

Resolution of the Pressure Locking Issue of Safety Related MOVs at NPP Krško

Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovatio
Latest Publications