scholarly journals A virtual test facility for simulating the dynamic response of materials

2000 ◽  
Vol 2 (2) ◽  
pp. 42-53 ◽  
Author(s):  
M. Aivazis ◽  
W.A. Goddard ◽  
D. Meiron ◽  
M. Ortiz ◽  
J. Pool ◽  
...  
Author(s):  
Kiminobu Hojo ◽  
Tadashi Kimura ◽  
Akio Kitada ◽  
Hiroshi Tamaki ◽  
Junich Kishimoto ◽  
...  

The nuclear spent fuel transport and storage cask is used for transport of the spent fuel from a nuclear power station to an intermediate storage facility. Leak tightness and subcriticality on transportation required from IAEA TS-R1 [1] have to be assured by a 9m drop test and its numerical simulation. This paper describes the drop test using a full-scale prototype test cask. The test was conducted by German Federal Institute for Materials Research and Testing (BAM) at their test facility in Horstwalde, Germany and comparison of the test result with the “MH1 (Mitsubishi Heavy Industries, Ltd.)” numerical simulation using LS-DYNA code. The drop orientations of the tests were slap down and vertical. From the drop test the following is demonstrated: • The leak rate of He gas after the drop tests satisfied the IAEA’s criteria. • The numerical simulation which modeled the cask body enabled dynamic response such as acceleration and strain of the cask body. This means the simulation method qualified the relation of dynamic response of the cask body and leakage behavior.


2020 ◽  
Vol MA2020-01 (3) ◽  
pp. 480-480
Author(s):  
Andrea Trovo' ◽  
Massimo Guarnieri

2006 ◽  
Vol 22 (3-4) ◽  
pp. 325-347 ◽  
Author(s):  
Ralf Deiterding ◽  
Raul Radovitzky ◽  
Sean P. Mauch ◽  
Ludovic Noels ◽  
Julian C. Cummings ◽  
...  

2020 ◽  
Vol MA2020-02 (6) ◽  
pp. 1037-1037
Author(s):  
Andrea Trovo ◽  
Nicola Poli ◽  
Massimo Guarnieri

Author(s):  
J. J. Laidler ◽  
B. Mastel

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.


Author(s):  
Edward Seckel ◽  
Ian A. M. Hall ◽  
Duane T. McRuer ◽  
David H. Weir
Keyword(s):  

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