scholarly journals Dynamic Response Testing in an Electrically Heated Reactor Test Facility

2006 ◽  
Author(s):  
Shannon M. Bragg-Sitton
Keyword(s):  
Dynamic Response ◽  
Test Facility ◽  
Reactor Test ◽  
Response Testing

Deuterium Driven D - T Fusion Reactor Test Facility

1986 ◽  
Vol 10 (3P2B) ◽  
pp. 1412-1417
Author(s):  
Robert E. Price ◽  
Geoffrey W. Shuy ◽  
James T. Woo
Keyword(s):  
Fusion Reactor ◽  
Test Facility ◽  
Reactor Test

Transient Reactor Test Facility Advanced Transient Shapes

2019 ◽  
Vol 205 (10) ◽  
pp. 1346-1353 ◽  
Author(s):  
Thomas Holschuh ◽  
Nicolas Woolstenhulme ◽  
Benjamin Baker ◽  
John Bess ◽  
Cliff Davis ◽  
...  
Keyword(s):  
Test Facility ◽  
Reactor Test

Features of Postfailure Fuel Behavior in Transient Overpower and Transient Undercooled/Overpower Tests in the Transient Reactor Test Facility

1992 ◽  
Vol 98 (1) ◽  
pp. 124-136 ◽  
Author(s):  
Robert C. Doerner ◽  
Theodore H. Bauer ◽  
James A. Morman ◽  
John W. Holland
Keyword(s):  
Test Facility ◽  
Reactor Test ◽  
Fuel Behavior

Behavior of Full-Scale Model Cask Under 9m Drop Test and Simulation

2006 ◽  
Author(s):  
Kiminobu Hojo ◽  
Tadashi Kimura ◽  
Akio Kitada ◽  
Hiroshi Tamaki ◽  
Junich Kishimoto ◽  
...  
Keyword(s):  
Numerical Simulation ◽  
Dynamic Response ◽  
Nuclear Power ◽  
Simulation Method ◽  
Full Scale ◽  
Drop Test ◽  
Scale Model ◽  
Test Facility ◽  
Spent Fuel ◽  
Federal Institute

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.

Loss-of-Flow Transient Reactor Test Facility Tests L6 and L7 with Irradiated Liquid-Metal Fast Breeder Reactor Type Fuel

1981 ◽  
Vol 52 (3) ◽  
pp. 331-341 ◽  
Author(s):  
Richard Simms ◽  
Gerald E. Marsh ◽  
Alan B. Rothman ◽  
George S. Stanford
Keyword(s):  
Liquid Metal ◽  
Test Facility ◽  
Fast Breeder Reactor ◽  
Reactor Test ◽  
Reactor Type ◽  
Type Fuel

Dynamic Response Analysis on a 9 Kw Vrfb Test Facility

2020 ◽  
Vol MA2020-01 (3) ◽  
pp. 480-480
Author(s):  
Andrea Trovo' ◽  
Massimo Guarnieri
Keyword(s):  
Dynamic Response ◽  
Test Facility ◽  
Response Analysis ◽  
Dynamic Response Analysis
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