scholarly journals A Consideration on Limits of Cold Working in Nuclear Construction

1975 ◽  
Vol 97 (2) ◽  
pp. 162-171 ◽  
Author(s):  
R. A. Moen ◽  
G. V. Smith
Keyword(s):  
Mechanical Properties ◽  
Elevated Temperature ◽  
Cold Working ◽  
Cold Work ◽  
Time Dependent ◽  
Subsequent Performance ◽  
Fast Breeder Reactors ◽  
Breeder Reactors ◽  
Materials Used ◽  
Work Level

Cold working of metals affects the mechanical properties of those metals. These effects are particularly important in the design, analysis and subsequent performance of materials used in elevated temperature nuclear construction. This paper provides an assessment of the effects of cold working on the time independent and time dependent mechanical properties of the materials most commonly encountered in liquid metal fast breeder reactors. The paper suggests specific reductions, as a function of time, temperature and cold work level, for those properties adversely affected. The final objective of this paper is to provide an assessment of the manner in which the Code now addresses fabrication effects and how it might make those assessments in the future.

Evaluation Procedures for Irradiation Effects and Sodium Environmental Effects for the Structural Design of Japanese Fast Breeder Reactors

2000 ◽  
Vol 123 (1) ◽  
pp. 49-57 ◽  
Author(s):  
Tai Asayama ◽  
Yasuhiro Abe ◽  
Noriko Miyaji ◽  
Mamoru Koi ◽  
Tomohiro Furukawa ◽  
...  
Keyword(s):  
Mechanical Properties ◽  
Environmental Effects ◽  
Structural Design ◽  
Neutron Fluence ◽  
Evaluation Procedure ◽  
Fast Breeder Reactor ◽  
Irradiation Effects ◽  
Creep Life ◽  
Fast Breeder Reactors ◽  
Breeder Reactors

In the structural design of fast breeder reactors, irradiation effects and sodium environmental effects on structural materials have to be taken into account. In this paper, firstly, an evaluation procedure for irradiation effects on the mechanical properties of 316FR (FBR Grade 316 stainless steel), which is a newly developed stainless steel for the Japanese demonstration fast breeder reactor, is proposed. The procedure gives a limit of accumulated fast neutron fluence E>0.1 MeV as a function of temperature, so that the minimum tensile fracture elongation of 10 percent, which is the threshold for material to stay ductile, is maintained. Furthermore, the procedure determined a creep life reduction factor and a creep rate increase factor as a function of accumulated thermal neutron fluence E<0.4 eV, within the limitation of the accumulated fast neutron fluence, to account for the creep life reduction and the increase of creep rate due to irradiation. Secondly, an evaluation procedure for sodium environmental effects on the integrity of 316FR and modified 9Cr-1Mo steel was proposed. It gave a corrosion allowance as a function of temperature, oxygen content, and service time, based on corrosion tests. It determined that no correction factors that correspond to sodium environment on design allowable stresses, etc., are needed, because no adverse effects of sodium on the mechanical properties of 316FR and modified 9Cr-1Mo steel were to be expected in the service conditions of FBRs. Both the procedures have been incorporated into the Japanese Elevated Temperature Structural Design Guide for Demonstration Fast Breeder Reactor.

Pressureless Sintering of B4C Neutron Absorbing Material with Nano-Sized Rare-Earth Compounds Addition

2012 ◽  
Vol 602-604 ◽  
pp. 503-507
Author(s):  
Ru Bin Wei ◽  
Yu Jun Zhang ◽  
Hong Yu Gong ◽  
Xiao Jun Liu ◽  
Ya Zhen Jiang ◽  
...  
Keyword(s):  
Mechanical Properties ◽  
Rare Earth ◽  
Boron Carbide ◽  
Pressureless Sintering ◽  
Rare Earth Compounds ◽  
Neutron Absorber ◽  
Absorbing Material ◽  
Fast Breeder Reactors ◽  
Dysprosium Titanate ◽  
Breeder Reactors

The processing of boron carbide by pressureless sintering with nano-sized rare-earth compounds additives to obtain dense pellets for use as neutron absorber in fast breeder reactors is investigated. The effect of dysprosium aluminum garnet (DAG) and dysprosium titanate nanopowders on density and mechanical properties was studied. The addition of DAG and dysprosium titanate nanopowders was found to be beneficial in the densification of B4C powders. B4C with 5 wt. % of DAG or dysprosium titanate nanopowders, exhibiting bulk density of 2.14g/cm3 and 2.35 g/cm3, could be prepared by pressureless heating at 2120°C and 2160°C.

Microstructure Refinement Effect on EUROFER 97 Steel for Nuclear Fusion Application

2021 ◽  
Vol 1016 ◽  
pp. 1392-1397
Author(s):  
Giulia Stornelli ◽  
Roberto Montanari ◽  
Claudio Testani ◽  
Luciano Pilloni ◽  
Giuseppe Napoli ◽  
...  
Keyword(s):  
Mechanical Properties ◽  
Pilot Scale ◽  
Detailed Knowledge ◽  
Mechanical Processing ◽  
Process Optimisation ◽  
First Wall ◽  
High Radiation ◽  
Fast Breeder Reactors ◽  
Breeder Reactors ◽  
Eurofer 97

In Europe EUROFER 97 has been recognised as reference steel for the nuclear costructions under high radiation density for first wall of a fast breeder reactors as well as in other high stressed primary structures such as the divertors, blanklet and vessels. Following to this a EUROFER 97 detailed knowledge of the microstructure evolution after thermo-mechanical processing is required, because the material mechanical properties are interesting also for innovative solar plants, i.e. NEXTOWER project. A detailed knowledge of process optimisation is mandatory because EUROFER 97 steel mechanical properties and microstruture are heavily influenced and improved (and easily affeted) by thermomechanical treatments. In this paper the effect of thermo-mechanical parameters on the grain refinement of EUROFER 97 has been investigated by cold rolling and heat treatment on pilot scale.

Modification of the Al0.9Zn0.05Sn0.05 Alloy Microstructure by Cold Working and Chemical Composition

MRS Advances ◽  
2017 ◽  
Vol 2 (64) ◽  
pp. 4049-4054
Author(s):  
M.L. Mendoza-López ◽  
M.E. Pérez-Ramos ◽  
G. Atanacio-Jiménez ◽  
J. Pérez-Meneses ◽  
M. Mexicano-Tovar ◽  
...  
Keyword(s):  
Mechanical Properties ◽  
Chemical Composition ◽  
Cold Working ◽  
Cold Work ◽  
Low Density ◽  
Metallic Elements ◽  
Subsequent Increase ◽  
Interdendritic Space ◽  
Alloy Microstructure ◽  
Aluminum Oxide Layer

ABSTRACTAluminum alloys have increased their use due to the properties such as low density, resistance to corrosion under environmental conditions and mechanical properties. In this work, the alloying elements are immiscible promoting dendrites formation with different phases attributed to zinc and tin. The applied mechanical stresses promoted the modification of the dendrite sizes (interdendritic space) as well as pore sizes and shapes. The microhardness decreased in the ternary Al-Zn-Sn alloy with a subsequent increase caused by microstructural changes after cold work. By XPS, the metallic elements were detected with an aluminum oxide layer.

Radiation Damage Studies with the HVEM

1972 ◽  
Vol 30 ◽  
pp. 680-681
Author(s):  
J. J. Laidler ◽  
B. Mastel
Keyword(s):  
Radiation Damage ◽  
Stainless Steels ◽  
Volume Expansion ◽  
Austenitic Stainless Steels ◽  
Test Facility ◽  
Fast Breeder Reactors ◽  
Breeder Reactors ◽  
Under Construction ◽  
Development Laboratory ◽  
Insight Into

One of the major materials problems encountered in the development of fast breeder reactors for commercial power generation is the phenomenon of swelling in core structural components and fuel cladding. This volume expansion, which is due to the retention of lattice vacancies by agglomeration into large polyhedral clusters (voids), may amount to ten percent or greater at goal fluences in some austenitic stainless steels. From a design standpoint, this is an undesirable situation, and it is necessary to obtain experimental confirmation that such excessive volume expansion will not occur in materials selected for core applications in the Fast Flux Test Facility, the prototypic LMFBR now under construction at the Hanford Engineering Development Laboratory (HEDL). The HEDL JEM-1000 1 MeV electron microscope is being used to provide an insight into trends of radiation damage accumulation in stainless steels, since it is possible to produce atom displacements at an accelerated rate with 1 MeV electrons, while the specimen is under continuous observation.

CARLSON ALLOY C600 and C600 ESR

Alloy Digest ◽  
1994 ◽  
Vol 43 (11) ◽  
Keyword(s):  
Mechanical Properties ◽  
Solid Solution ◽  
Fracture Toughness ◽  
Cold Working ◽  
Elevated Temperatures ◽  
High Strength ◽  
Heat Treating ◽  
Solid Solution Alloy ◽  
Resistance To Oxidation ◽  
Good Workability

Abstract CARLSON ALLOYS C600 AND C600 ESR have excellent mechanical properties from sub-zero to elevated temperatures with excellent resistance to oxidation at high temperatures. It is a solid-solution alloy that can be hardened only by cold working. High strength at temperature is combined with good workability. This datasheet provides information on composition, physical properties, elasticity, and tensile properties as well as fracture toughness. It also includes information on corrosion resistance as well as forming, heat treating, and machining. Filing Code: Ni-470. Producer or source: G.O. Carlson Inc.

ALMAR 300 ALLOY

Alloy Digest ◽  
1978 ◽  
Vol 27 (7) ◽  
Keyword(s):  
Corrosion Resistance ◽  
Elevated Temperature ◽  
Cold Working ◽  
High Strength ◽  
Heat Treating ◽  
Age Hardening ◽  
Ultra High Strength Steel ◽  
Wide Range ◽  
Iron Nickel ◽  
Useful Yield

Abstract ALMAR 300 Alloy is a vacuum-melted ultra-high-strength steel. The annealed structure of this alloy is essentially a carbon-free, iron-nickel martensite (a relatively soft Rockwell C 28) that can be strengthened by cold working and elevated-temperature (900-950 F) age hardening to useful yield strengths as high as 300,000 psi. The unique properties of this alloy make it suitable for a wide range of section sizes. This datasheet provides information on composition, physical properties, hardness, elasticity, and tensile properties. It also includes information on corrosion resistance as well as forming, heat treating, machining, and joining. Filing Code: SA-349. Producer or source: Allegheny Ludlum Corporation.

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