scholarly journals Design of Radiation-Tolerant Structural Alloys for Generation IV Nuclear Energy Systems

2005 ◽  
Author(s):  
T.R. Allen ◽  
G.S. Was ◽  
S.M. Bruemmer ◽  
J. Gan ◽  
S. Ukai
Keyword(s):  
Nuclear Energy ◽  
Energy Systems ◽  
Radiation Tolerant

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.

scholarly journals Elaboration of approach to nuclear energy systems assessment by criterion of sustainable development

2018 ◽  
Vol 4 (1) ◽  
pp. 27-33
Author(s):  
Vladimir I. Usanov ◽  
Stepan A. Kviatkovskii ◽  
Andrey A. Andrianov
Keyword(s):  
Sustainable Development ◽  
Nuclear Fuel ◽  
Nuclear Energy ◽  
Spent Nuclear Fuel ◽  
Fuel Cycle ◽  
Energy Systems ◽  
Nuclear Fuel Cycle ◽  
Time Interval ◽  
Subject Areas ◽  
Key Events

The paper describes the approach to the assessment of nuclear energy systems based on the integral indicator characterizing the level of their sustainability and results of comparative assessment of several nuclear energy system options incorporating different combinations of nuclear reactors and nuclear fuel cycle facilities. The nuclear energy systems are characterized by achievement of certain key events pertaining to the following six subject areas: economic performance, safety, availability of resources, waste handling, non-proliferation and public support. Achievement of certain key events is examined within the time interval until 2100, while the key events per se are assessed according to their contribution in the achievement of sustainable development goals. It was demonstrated that nuclear energy systems based on the once-through nuclear fuel cycle with thermal reactors and uranium oxide fuel do not score high according to the integral sustainable development indicator even in the case when the issue of isolation of spent nuclear fuel in geological formation is resolved. Gradual replacement of part of thermal reactors with fast reactors and closing the nuclear fuel cycle results in the achievement of evaluated characteristics in many subject areas, which are close to maximum requirements of sustainable development, and in the significant enhancement of the sustainability indicator.

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.

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