Investigation of the corrosion resistance of fuel micropellet cladding made of silicon carbide and pyrolytic carbon for the operating conditions of light-water reactors in nuclear power plants

Atomic Energy ◽  
2006 ◽  
Vol 101 (4) ◽  
pp. 722-729 ◽  
Author(s):  
G. A. Filippov ◽  
E. I. Grishanin ◽  
M. V. Konditerov ◽  
V. P. Mastyukin ◽  
V. I. Mel’kin ◽  
...  
Keyword(s):  
Silicon Carbide ◽  
Corrosion Resistance ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Pyrolytic Carbon ◽  
Operating Conditions ◽  
Light Water Reactors ◽  
Light Water ◽  
Water Reactors

Underground Siting of Nuclear Power Plants: Insights From Fukushima

2012 ◽  
Author(s):  
Jay F. Kunze ◽  
James M. Mahar ◽  
Kellen M. Giraud ◽  
C. W. Myers
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Light Water Reactors ◽  
Light Water ◽  
Waste Storage ◽  
Small Modular Reactor ◽  
Fukushima Daiichi ◽  
Water Reactors ◽  
High Level

Siting of nuclear power plants in an underground nuclear park has been proposed by the authors in many previous publications, first focusing on how the present 1200 to 1600 MW-electric light water reactors could be sited underground, then including reprocessing and fuel manufacturing facilities, as well as high level permanent waste storage. Recently the focus has been on siting multiple small modular reactor systems. The recent incident at the Fukushima Daiichi site has prompted the authors to consider what the effects of a natural disaster such as the Japan earthquake and subsequent tsunami would have had if these reactors had been located underground. This paper addresses how the reactors might have remained operable — assuming the designs we previously proposed — and what lessons from the Fukushima incident can be learned for underground nuclear power plant designs.

Life Beyond 60 Years: The Importance of Sustaining the Current Fleet of Light Water Reactors in the U.S. and the R&D Needs

2010 ◽  
Author(s):  
Ronaldo Szilard ◽  
Hongbin Zhang
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Superior Performance ◽  
Light Water Reactors ◽  
Economic Operation ◽  
Significant Interest ◽  
Water Reactors ◽  
The U.S

The current fleet of 104 nuclear power plants in the U.S. began their operation with 40 years operating licenses. About half of these plants have their licenses renewed to 60 years and most of the remaining plants are anticipated to pursue license extension to 60 years. With the superior performance of the current fleet and formidable costs of building new nuclear power plants, there has been significant interest to extend the lifetime of the current fleet even further from 60 years to 80 years. This paper addresses some of the key long term technical challenges and identifies R&D needs related to the long term safe and economic operation of the current fleet.

Comparison of Nuclear Fitness for Service Codes: ASME Section XI and RSE-M AFCEN Codes

2014 ◽  
Author(s):  
Claude Faidy
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Light Water Reactors ◽  
Pressurized Water ◽  
Term Operation ◽  
Mechanical Components ◽  
Water Reactors ◽  
Test Requirements ◽  
Service Inspection

Two major Codes are used for Fitness for Service of Nuclear Power Plants: one is the ASME B&PV Code Section XI and the other one is the French RSE-M Code. Both of them are largely used in many countries, partially or totally. The last 2013 RSE-M covers “Mechanical Components of Pressurized Water Reactors (PWRs): - Pre-service and In-service inspection - Surveillance in operation or during shutdown - Flaw evaluation - Repairs-Replacements parts for plant in operation - Pressure tests The last 2013 ASME Section XI covers “Mechanical components and containment of Light Water Reactors (LWRs)” and has a larger scope with similar topics: more types of plants (PWR and Boiling Water Reactor-BWR), other components like metallic and concrete containments… The paper is a first comparison covering the scope, the jurisdiction, the general organization of each section, the major principles to develop In Service Inspection, Repair-Replacement activities, the flaw evaluation rules, the pressure test requirements, the surveillance procedures (monitoring…) and the connections with Design Codes… These Codes are extremely important for In-service inspection programs in particular and essential tools to justify long term operation of Nuclear Power Plants.

scholarly journals Heat in a Bottle

2019 ◽  
Vol 141 (01) ◽  
pp. 36-41 ◽  
Author(s):  
Charles W. Forsberg
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Heat Storage ◽  
Light Water Reactors ◽  
Enabling Technology ◽  
Light Water ◽  
Nuclear Plants ◽  
Water Reactors ◽  
Storage Technologies ◽  
Current Heat

Concentrated solar plants have been designed to store thermal energy so as to produce power after sundown, but heat storage should also be of interest to operators of nuclear power plants. Adding heat storage to light-water reactors is the enabling technology for a carbon-free electricity industry based on solar, wind, and nuclear power. And it can accomplish this with little disruption to the operations of existing nuclear plants. This article delves into the current heat storage technologies that are at various states of readiness to be deployed.

Role of Deterministic Design Safety Criteria in Assuring Safety of Generation IV Reactors

2009 ◽  
Author(s):  
Sang Kyu Ahn ◽  
Inn Seock Kim ◽  
Hun-Joo Lee ◽  
Soon Joon Hong
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Light Water Reactors ◽  
Light Water ◽  
Safe Production ◽  
Analysis Technique ◽  
Power Safety ◽  
Water Reactors ◽  
Shed Light

In the nuclear power community, deterministic design safety criteria have been used as a major means for assuring safety of nuclear power plants, e.g., light water reactors (LWRs). However, as a result of considerable advances in the quantitative risk analysis technique, such as Probabilistic Risk Assessment (PRA), risk-informed approaches are increasingly applied together with some of the deterministic approaches that are still considered valid. In this paper, the various deterministic approaches that have played an important role in ensuring nuclear power safety are critically reviewed to shed light to the necessary characteristics of the desirable design safety criteria especially with regard to advanced reactors such as Generation IV reactors that have great potential to further enhance the economic and safe production of nuclear power.

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