FUEL ROD EXPERIENCE DURING THE SPERT I DESTRUCTIVE TEST SERIES WITH A STAINLESS STEEL CLAD, ROD-TYPE CORE

Leak tightness of magnetic pulse crimped joints

International Journal Sustainable Construction & Design ◽

10.21825/scad.v3i3.20580 ◽

2012 ◽

Vol 3 (3) ◽

pp. 243-250

Author(s):

A. Loosveld ◽

W. De Waele ◽

K. Faes ◽

O. Zaitov

Keyword(s):

Stainless Steel ◽

Steel Tube ◽

Test Series ◽

Stainless Steel Tube ◽

Magnetic Pulse ◽

Test Procedures ◽

Burst Test ◽

Master Thesis ◽

Leak Tightness ◽

Sealing Materials

The goal of this master thesis is to realize and investigate leak tightness of joints produced by theelectromagnetic pulse (EMP) crimping process. This way of joining metals has gained more attention lately.With EMP welding, leak tight joints can already be achieved. However, the crimping process has somemajor advantages over EMP welding like the fact that more material combinations are possible and itrequires less energy. To realize the leak tightness, two kinds of sealing materials are used: O-rings andadhesives. The workpieces consist of an aluminium or stainless steel tube which is crimped on a solidaluminium mandrel with circumferential grooves in it. First, some preliminary tests are performed todetermine how much the tubes deform in the grooves. This deformation mainly depends on the appliedcharging voltage and the geometry of the groove. With this information, it is possible to estimate the amountof compression an O-ring would undergo when placed inside this groove. On other workpieces, adhesiveswill be applied. Several test procedures can be conducted on the parts to investigate leak tightness. Theresults of a helium test and a pressure burst test on the first test series conducted at the Walloon researchcentre CEWAC already showed that the use of O-rings can be effective.

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Investigation of stainless steel clad fuel rod failures and fuel performance in the Connecticut Yankee Reactor. Final report

10.2172/5160258 ◽

1981 ◽

Cited By ~ 2

Author(s):

V. Pasupathi ◽

R. W. Klingensmith

Keyword(s):

Stainless Steel ◽

Final Report ◽

Fuel Performance ◽

Fuel Rod

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Numerical investigations of stainless steel melt motions on the surface of uranium dioxide

EPJ Web of Conferences ◽

10.1051/epjconf/201919600005 ◽

2019 ◽

Vol 196 ◽

pp. 00005 ◽

Cited By ~ 1

Author(s):

Eduard V. Usov ◽

Pavel D. Lobanov ◽

Ilya A. Klimonov ◽

Alexander E. Kutlimetov ◽

Anton A. Butov ◽

...

Keyword(s):

Stainless Steel ◽

Uranium Dioxide ◽

Momentum Conservation ◽

Mass Energy ◽

Numerical Investigations ◽

Fuel Rod ◽

The Core ◽

Fuel Pin ◽

Energy And Momentum ◽

Coolant Velocity

The paper contains the results of numerical simulation of stainless steel melt motions on the surface of uranium dioxide. The investigations are performed for purposes of understanding of the fuel rod behavior during the core disruptive accident in the fast reactors. The systems of mass, energy and momentum conservation equations are solved to simulate melt motion on the surface of the fuel pin. Heat transfer and friction between melt and pin's surface and melt and coolant flow are taken into consideration. The dependences of mass of the melt and the features of the melt motion on coolant velocity and contact angle between melt and surface of the fuel rod are presented.

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Comparison Between ASME Code-Case N-761, NUREG/CR-6909 and Stainless Steel Component Fatigue Test Results

Volume 1: Codes and Standards ◽

10.1115/pvp2014-28883 ◽

2014 ◽

Author(s):

H. T. Harrison ◽

Robert Gurdal

Keyword(s):

Stainless Steel ◽

Fatigue Test ◽

Fatigue Tests ◽

Test Series ◽

Test Results ◽

Actual Number ◽

Steel Component ◽

Class 1 ◽

Asme Code ◽

Number Of Cycles

For Class 1 components, the consideration of the environmental effects on fatigue has been suggested to be evaluated through two different methodologies: either NUREG/CR-6909 from March 2007 or ASME-Code Case N-761 from August 2010. The purpose of this technical paper is to compare these two methods. In addition, the equations from Revision 1 of the NUREG/CR-6909 will be evaluated. For these comparisons, two stainless steel component fatigue test series with documented results are considered. These two fatigue test series are completely different from each other (applied cyclic displacements vs. insurge/outsurge types of transients). Therefore, they are producing an appropriate foundation for these comparisons. In general, the severities of the two methods are compared, where the severity is defined as the actual number of cycles from the fatigue tests, including an evaluation of the scatter, divided by the number of design cycles from the two methods. Also, how stable the methods are is being evaluated through the calculation of the coefficient of variation for each method.

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Failure Behavior of Stainless Steel Clad Fuel Rod under Simulated Reactivity Initiated Accident Condition

Journal of Nuclear Science and Technology ◽

10.1080/18811248.1986.9735097 ◽

1986 ◽

Vol 23 (12) ◽

pp. 1051-1063

Author(s):

Shusaku SHIOZAWA ◽

Shinzo SAITO

Keyword(s):

Stainless Steel ◽

Failure Behavior ◽

Fuel Rod ◽

Accident Condition

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Analysis of Computer Modelling Results on Fuel Rods Strength and Condition at Reduced or Absent Cooling Caused by Accident

Energy Engineering and Control Systems ◽

10.23939/jeecs2021.01.007 ◽

2021 ◽

Vol 7 (1) ◽

pp. 7-16

Author(s):

Stepan Lys ◽

Keyword(s):

Stainless Steel ◽

Fuel Assembly ◽

Computer Modelling ◽

Severe Accident ◽

Research Centre ◽

Steel Component ◽

Spacer Grids ◽

Fuel Rod ◽

Standard Problem ◽

Post Test

The paper describes the phenomenology of fuel rod behaviour in severe accident. As an example, an experiment is described resulting in severe damage of 19 fuel rod assembly of VVER type; it was carried out in the CORA facility in 1993 (Research Centre, Karlsruhe, Germany). Testing conditions and results of post-test investigations of fuel assembly are given. The fuel rod code RAPTA-SFD is briefly dealt with; the code was a participant in the International Standard Problem ISP-36. The basic results are presented acquired by computer modelling CORA-W2 experiment using RAPTA-SFD code. Among the presented experimentally acquired and calculated results, the scope of the data on stainless steel component behaviour is substantial. The tested CORA-W2 fuel assembly contained a significant quantity of steel components, viz., spacer grids, a guide thimble, and a cladding of an absorber element. It is to be borne in mind that the spacer grids and a guide thimble of the updated and upgraded fuel assembly of VVER-1000 are fabricated from Zr-alloy, hence, the relative quantitative characteristics of chemical interactions between materials and stainless steel (Cr-Ni alloy) will be much lower for the up-to-date upgraded fuel assembly under identical conditions.

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