A Review of Alloy 800H for Applications in the Gen IV Nuclear Energy Systems

2010 ◽  
Author(s):  
Weiju Ren ◽  
Robert Swindeman
Keyword(s):  
Research And Development ◽  
Environmental Effect ◽  
Nuclear Energy ◽  
Energy Systems ◽  
Extensive Review ◽  
Nuclear System ◽  
Alloy 800H ◽  
Aging Resistance ◽  
Gen Iv ◽  
Data Requirements

Alloy 800H is currently under consideration for applications in the Next Generation Nuclear Plant at operational temperatures above 750°C. To provide supporting information in this paper at the attempt to facilitate the consideration, service requirements of the nuclear system for structural materials is first described; and then an extensive review of Alloy 800H is given on its codification with respect to development and research history, mechanical behavior and design allowables, metallurgical aging resistance, environmental effect considerations, data requirements and availability, weldments, as well as many other aspects relevant to the intended nuclear application; an finally further research and development activities to support the materials qualification are suggested.

Status of Alloy 800 H in Considerations for the Gen IV Nuclear Energy Systems

2014 ◽  
Vol 136 (5) ◽  
Author(s):  
Weiju Ren ◽  
Robert Swindeman
Keyword(s):  
Research And Development ◽  
Environmental Effect ◽  
Nuclear Energy ◽  
Energy Systems ◽  
Extensive Review ◽  
Nuclear System ◽  
Alloy 800 ◽  
Aging Resistance ◽  
Gen Iv ◽  
Data Requirements

Alloy 800 H is currently under consideration for applications in the next generation nuclear plant (NGNP) at operational temperatures above 750 °C. This paper first describes service requirements of the nuclear system for structural materials; and then an extensive review of Alloy 800 H is given on its codification with respect to development and research history, mechanical behavior and design allowables, metallurgical aging resistance, environmental effect considerations, data requirements and availability, weldments, as well as many other aspects relevant to the intended nuclear application. Finally, further research and development activities to support the materials qualification are suggested.

scholarly journals The Supersafe© Reactor: A Small Modular Pressure Tube SCWR

2012 ◽  
Vol 1 (2) ◽  
pp. 13-18 ◽  
Author(s):  
M. Yetisir ◽  
J. Pencer ◽  
M. McDonald ◽  
M. Gaudet ◽  
J. Licht ◽  
...  
Keyword(s):  
Research And Development ◽  
Supercritical Water ◽  
Nuclear Energy ◽  
Energy Systems ◽  
Full Scale ◽  
Development Effort ◽  
Gen Iv ◽  
Energy Grid ◽  
Supercritical Water Cooled Reactor ◽  
Primary Contribution

The SUPERSAFE© Reactor (SSR) is proposed as a small modular version of the Canadian supercritical water-cooled reactor (SCWR). The SCWR is Canada’s primary contribution to the Generation-IV (GEN-IV) International Forum’s (GIF) research and development effort toward the study and eventual deployment of advanced nuclear energy systems. All GEN-IV concepts, including the SCWR, have enhanced safety, improved economics, improved sustainability and enhanced security compared to contemporary reactors. The SUPERSAFE© Reactor (SSR) concept incorporates the enhanced features of the SCWR in a smaller core which could be deployed in areas with sparsely distributed population bases where it is impractical to have a full scale SCWR or large centralized energy grid. An overview of the SSR concept is presented in this work.

scholarly journals Gen IV Nuclear Energy Systems Interim Status Report on Pre-conceptual LFR Design Studies and Evaluations

2005 ◽  
Author(s):  
W Halsey ◽  
N Brown ◽  
C Smith ◽  
J Sienicki ◽  
A Moisseytsev ◽  
...  
Keyword(s):  
Nuclear Energy ◽  
Energy Systems ◽  
Status Report ◽  
Design Studies ◽  
Gen Iv

Materials for future nuclear energy systems

2019 ◽  
Vol 527 ◽  
pp. 151837 ◽  
Author(s):  
G.S. Was ◽  
D. Petti ◽  
S. Ukai ◽  
S. Zinkle
Keyword(s):  
Nuclear Energy ◽  
Energy Systems

Cross-Comparison of One-Dimensional Thermal-Hydraulic Codes on Natural Circulation Analysis of NACIE Loop Test for Lead-Alloy Cooled Advanced Nuclear Energy Systems (LACANES)

2014 ◽  
Author(s):  
Yong-Hoon Shin ◽  
Il Soon Hwang ◽  
Massimiliano Polidori ◽  
Paride Meloni ◽  
Vincenzo Casamassima ◽  
...  
Keyword(s):  
Phase I ◽  
Phase Ii ◽  
Nuclear Energy ◽  
Natural Circulation ◽  
Energy Systems ◽  
Research Centre ◽  
Hydraulic Loss ◽  
Lead Alloy ◽  
Test Results ◽  
One Dimensional

As one of the Generation-IV reactor concepts, lead-alloy-cooled advanced nuclear energy systems (LACANES) have been studied worldwide in order to utilize the advantages of good heat transfer properties, neutron transparency and chemical inertness with air and water. Since the Fukushima accident, the passive safety aspect of the LACANES is increasingly emphasized due to outstanding natural circulation capability. To investigate the thermal-hydraulic capability of LBE, an international cooperation has been performed under OECD/NEA program, under the guidance of the Nuclear Science Committee by a task force named as Lead Alloy Cooled Advanced Nuclear Energy Systems (LACANES) since 2007. This international collaboration had dealt with computational benchmarking of isothermal LBE forced convection tests in the phase I, and the working group published a guideline for using one-dimensional system codes to simulate LBE forced circulation test results from HELIOS loop. The phase II was started after that, to give an additional guideline in the case of natural circulation. NACIE, one of benchmarking targets for the phase II which is a rectangular-shape loop located at ENEA-Brasimone Research Centre, Italy. NACIE test results were benchmarked by each participant using their one-dimensional thermal-hydraulic codes, and they are to follow the guideline from the LACANES phase I for regions where hydraulic loss occurs. Due to the selection of hydraulic loss coefficient relations by users, the cross-comparison results of international participants showed some discrepancies and the estimated mass flow rates had 13% of maximum error. Also, the future R&D areas are identified.

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