scholarly journals FABRICATION COSTS FOR PLUTONIUM FUEL ELEMENTS. PART B . VARIABLE COSTS OF FABRICATING UO$sub 2$-PuO$sub 2$ FUEL RODS FOR THE EXPERIMENTAL BOILING WATER REACTOR

1965 ◽  
Author(s):  
C Bloomster
Keyword(s):  
Boiling Water ◽  
Boiling Water Reactor ◽  
Fuel Rods ◽  
Water Reactor ◽  
Plutonium Fuel ◽  
Fuel Elements ◽  
Fabrication Costs

scholarly journals Measurement station for interim inspections of Lightbridge metallic fuel rods at the Halden Boiling Water Reactor

2018 ◽  
Vol 170 ◽  
pp. 04011 ◽  
Author(s):  
C. Hartmann ◽  
A. Totemeier ◽  
S. Holcombe ◽  
J. Liverud ◽  
M. Limi ◽  
...  
Keyword(s):  
Cross Section ◽  
Eddy Current ◽  
Boiling Water ◽  
Third Party ◽  
Boiling Water Reactor ◽  
Bonding Layer ◽  
Metallic Fuel ◽  
Fuel Rods ◽  
Water Reactor ◽  
Probe Geometry

Lightbridge Corporation has developed a new Uranium-Zirconium based metallic fuel. The fuel rods aremanufactured via a co-extrusion process, and are characterized by their multi-lobed (cruciform-shaped) cross section. The fuel rods are also helically-twisted in the axial direction. Two experimental fuel assemblies, each containing four Lightbridge fuel rods, are scheduled to be irradiated in the Halden Boiling Water Reactor (HBWR) starting in 2018. In addition to on-line monitoring of fuel rod elongation and critical assembly conditions (e.g. power, flow rates, coolant temperatures, etc.) during the irradiation, several key parameters of the fuel will be measured out-of-core during interim inspections. An inspection measurement station for use in the irradiated fuel handling compartment at the HBWR has therefore been developed for this purpose. The multi-lobed cladding cross section combined with the spiral shape of the Lightbridge metallic fuel rods requires a high-precision guiding system to ensure good position repeatability combined with low-friction guiding. The measurement station is equipped with a combination of instruments and equipment supplied from third-party vendors and instruments and equipment developed at Institute for Energy Technology (IFE). Two sets of floating linear voltage differential transformer (LVDT) pairs are used to measure swelling and diameter changes between the lobes and the valleys over the length of the fuel rods. Eddy current probes are used to measure the thickness of oxide layers in the valleys and on the lobe tips and also to detect possible surface cracks/pores. The measurement station also accommodates gamma scans. Additionally, an eddy-current probe has been developed at IFE specifically to detect potential gaps or discontinuities in the bonding layer between the metallic fuel and the Zirconium alloy cladding. Potential gaps in the bonding layer will be hidden behind a 0.5-1.0 mm thick cladding wall. It has therefore been necessary to perform a careful design study of the probe geometry. For this, finite element analysis (FEA) has been performed in combination with practical validation tests on representative fuel dummies with machined flaws to find the probe geometry that best detects a hidden flaw. Tests performed thus far show that gaps down to 25 μm thickness can be detected with good repeatability and good discrimination from lift-off signals.

Characterization of corrosion products deposited on fuel rods in a boiling water reactor (BWR-6) plant using hydrogen water chemistry (HWC)

2013 ◽  
Vol 298 (2) ◽  
pp. 1235-1244 ◽  
Author(s):  
Tsuey-Lin Tsai ◽  
Tzung-Yi Lin ◽  
Te-Yen Su ◽  
Tung-Jen Wen ◽  
Lee-Chung Men
Keyword(s):  
Water Chemistry ◽  
Corrosion Products ◽  
Boiling Water ◽  
Boiling Water Reactor ◽  
Fuel Rods ◽  
Water Reactor ◽  
Hydrogen Water

Corrosion Optimized Zircaloy for Boiling Water Reactor (BWR) Fuel Elements

2009 ◽  
pp. 709-709-15 ◽  
Author(s):  
F Garzarolli ◽  
R Schumann ◽  
E Steinberg
Keyword(s):  
Boiling Water ◽  
Boiling Water Reactor ◽  
Water Reactor ◽  
Fuel Elements

Power Flattening on Design Study of Small Long-Life Boiling Water Reactor (BWR) with Tight Lattice Thorium Nitride Fuel

2015 ◽  
Vol 751 ◽  
pp. 257-262 ◽  
Author(s):  
Nuri Trianti ◽  
Su'ud Zaki ◽  
Idam Arif ◽  
Sidik Permana ◽  
Eka Sapta Riyana
Keyword(s):  
Reactor Core ◽  
Life Time ◽  
Boiling Water ◽  
Boiling Water Reactor ◽  
Operating Life ◽  
Water Reactor ◽  
Nitride Fuel ◽  
Fuel Elements ◽  
Tight Lattice ◽  
Power Flattening

Preliminary study of thorium based fuel utilization with the addition of Pa-231 on tight lattice boiling water reactor (BWR) has been performed. In previous studies, the use of fuel composition Th-232 and U-233 as well as the use of protactinium as burnable poisons with hexagonal tight lattice fuel cell geometry has resulted the reactor life time of 30 years without refueling [1]. In this study, power flattening has been conducted on the reactor core by using radially heterogeneous fuel. Addition of the Pa-231 is expected to extend lifetime of the BWR core By optimizing the composition of the fuel elements (Th and Pa) at low moderation conditions (tight lattice) it can be obtained the reactor core which can be opeprated over 30 years without refueling or fuel shuffling. The Reactor core has a volume of 17,635.8 liter, power of 620 MWt, operating life of 30 and a maximum excess reactivity value of 0.384% dk/k, could be achieved by using a composition of U-233 enrichment of 8.1 to 11% and the addition of Pa-231 as much as 6.16 to 11.13% with a power density of 35.2 watts/cc.

scholarly journals FABRICATION OF SPIKED-CORE FUEL ELEMENTS FOR THE EXPERIMENTAL BOILING WATER REACTOR. Final Report

1965 ◽  
Author(s):  
W.C. Kramer ◽  
F.D. McCuaig ◽  
R.A. Beatty ◽  
C.H. Bean ◽  
R.A. Noland
Keyword(s):  
Boiling Water ◽  
Boiling Water Reactor ◽  
Final Report ◽  
Water Reactor ◽  
Fuel Elements

The Behavior of Breached Boiling Water Reactor Fuel Rods on Long-Term Exposure to Air and Argon at 598 K

1985 ◽  
Vol 69 (2) ◽  
pp. 186-197 ◽  
Author(s):  
R. Kohli ◽  
D. Stahl ◽  
V. Pasupathi ◽  
A. B. Johnson ◽  
E. R. Gilbert
Keyword(s):  
Reactor Fuel ◽  
Boiling Water ◽  
Boiling Water Reactor ◽  
Fuel Rods ◽  
Water Reactor
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