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Preliminary design of I-loops in ATR for irradiation testing of LWR fuels
N. S. Oldham
,
N. E. Woolstenhulme
,
K. R. Horman
, J. L. Peterson-Droogh
, T. L. Maddock
,
D. M. Wachs
Applied Engineering
Nuclear Fuels & Materials
Nuclear Science & Technology
Research output
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›
peer-review
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Keyphrases
Radiation Test
100%
Halden
100%
LWR Fuel
100%
Boiling Water Reactor
75%
Rodlet
75%
Prototypic
50%
Flux Trapping
50%
Capability Gap
50%
Fuel Irradiation
25%
Heating Rate
25%
Safety Assessment
25%
Reflector
25%
Neutron Flux
25%
Burnup
25%
Reactivity Control
25%
Irradiation
25%
Reactor Pressure Vessel
25%
In-pile
25%
Testing Capability
25%
PWR Fuel Rods
25%
Shimming
25%
High Availability
25%
Plumbing
25%
Design Evaluation
25%
Active Core
25%
I-positions
25%
Control Cylinder
25%
Beryllium Reflector
25%
Top Closure
25%
Rod Heating
25%
Loop Conditions
25%
Engineering
Preliminary Design
100%
Boiling Water Reactor
100%
Test Train
66%
Burnup
33%
Fuel Rod
33%
Reactivity Control
33%
Neutron Flux
33%
Reactor Pressure Vessel
33%
Heating Rate
33%
High Availability
33%
Control Cylinder
33%
Shims
33%