Brittle failure resistance of steels and weld metals for pressure vessels of light-water reactors

1986 ◽  
Vol 57 (11) ◽  
pp. 593-595
Author(s):  
Václav Pilous
Keyword(s):  
Brittle Failure ◽  
Pressure Vessels ◽  
Light Water Reactors ◽  
Light Water ◽  
Failure Resistance ◽  
Weld Metals ◽  
Brittle Failure Resistance ◽  
Water Reactors

Advanced Structural Materials and Cladding

MRS Bulletin ◽  
2009 ◽  
Vol 34 (1) ◽  
pp. 20-27 ◽  
Author(s):  
T. Allen ◽  
H. Burlet ◽  
R.K. Nanstad ◽  
M. Samaras ◽  
S. Ukai
Keyword(s):  
High Temperature ◽  
Structural Materials ◽  
Ceramic Composites ◽  
Pressure Vessels ◽  
Austenitic Steels ◽  
High Temperature Strength ◽  
Light Water Reactors ◽  
Modeling Tools ◽  
Light Water ◽  
Water Reactors

AbstractAdvanced nuclear energy systems, both fission- and fusion-based, aim to operate at higher temperatures and greater radiation exposure levels than experienced in current light water reactors. Additionally, they are envisioned to operate in coolants such as helium and sodium that allow for higher operating temperatures. Because of these unique environments, different requirements and challenges are presented for both structural materials and fuel cladding. For core and cladding applications in intermediate-temperature reactors (400–650°C), the primary candidates are 9–12Cr ferritic–martensitic steels (where the numbers represent the weight percentage of Cr in the material, i.e., 9–12 wt%) and advanced austenitic steels, adapted to maximize high-temperature strength without compromising lower temperature toughness. For very high temperature reactors (>650°C), strength and oxidation resistance are more critical. In such conditions, high-temperature metals as well as ceramics and ceramic composites are candidates. For all advanced systems operating at high pressures, performance of the pressure boundary materials (i.e., those components responsible for containing the high-pressure liquids or gases that cool the reactor) is critical to reactor safety. For some reactors, pressure vessels are anticipated to be significantly larger and thicker than those used in light water reactors. The properties through the entire thickness of these components, including the effects of radiation damage as a function of damage rate, are important. For all of these advanced systems, optimizing the microstructures of candidate materials will allow for improved radiation and high-temperature performance in nuclear applications, and advanced modeling tools provide a basis for developing optimized microstructures.

Ensuring the Performance of Nuclear Reactor Pressure Vessels for Long-Time Service

2010 ◽  
Author(s):  
Randy K. Nanstad ◽  
G. Robert Odette ◽  
Mikhail A. Sokolov
Keyword(s):  
Pressure Vessels ◽  
High Dose ◽  
Critical Element ◽  
Light Water Reactors ◽  
Time Service ◽  
Light Water ◽  
Time Operation ◽  
Long Time ◽  
Water Reactors ◽  
Reactor Pressure

Structural integrity of the reactor pressure vessel is a critical element in demonstrating the capability of light water reactors for operation to at least 80 y. The Light Water Reactor Sustainability Program Plan is a collaborative program between the U.S. Department of Energy and the private sector directed at extending the life of the present generation of nuclear power plants to enable such long-time operation. Given that the current generation of light water reactors were intended to operate for 40 y, there are significant issues that need to be addressed to reduce the uncertainties in regulatory application. The neutron dose to the vessel will at least double, and the database for such high dose levels under the low flux conditions in the vessel is nonexistent. Associated with this factor are uncertainties regarding flux effects, effects of relatively high nickel content, uncertainties regarding application of fracture mechanics, thermal annealing and reirradiation. The issue of high neutron fluence/long irradiation times and flux effects is the highest priority. Both data and mechanistic understanding are needed to enable accurate, reliable embrittlement predictions at high fluences. This paper discusses the major issues associated with long-time operation of existing RPVs, the LWRSP plans to address those issues, and recent relevant results.

A new approach to spent nuclear fuel recycling for light water reactors in the frame of remix concept

2020 ◽  
Vol 2020 (1) ◽  
pp. 67-77
Author(s):  
Nikita Vladimirivich Kovalyov ◽  
Boris Yakovlevich Zilberman ◽  
Nikolay Dmitrievich Goletskiy ◽  
Andrey Borisovich Sinyukhin
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Light Water Reactors ◽  
New Approach ◽  
Light Water ◽  
Water Reactors
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