Design and Thermal Analysis for Irradiation of Absorber Material Specimens in the High Flux Isotope Reactor

Cetiner, Nesrin Ozgan; Petrie, Christian M.; Burns, Joseph R.; Coq, Annabelle G. Le; Linton, Kory; Stevens, Jacqueline

doi:10.2172/1484111

Cited by 2 publications

(3 citation statements)

References 4 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The thermal analyses described in Cetiner et al [1] were revised to consider the peak HGRs calculated in the previous section (see Table 1). Table 2 shows the absorber materials properties used in this calculation.…”

Section: Thermal Analysesmentioning

confidence: 99%

“…Swelling will be measured by comparing specimen dimensions before and after irradiation to two different neutron fluence levels. The experiment design concept is detailed in Cetiner et al [1] and shown in Figure 1. This report presents the updated neutronics and thermal analyses, the pre-irradiation characterization of the specimens, and summarizes the assembly of two rabbits containing absorber material specimens.…”

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

Assembly and Delivery of Capsules for Irradiation of Absorber Material Specimens in the High Flux Isotope Reactor

Coq¹,

Cetiner²,

Burns³

et al. 2019

View full text Add to dashboard Cite

This report provides a summary of the thermal analysis, test matrix, and assembly of two capsules containing absorber material specimens. Four different absorber materials are inserted in the same capsule: hafnium carbide, hafnium carbide with a molybdenum silicide additive, samarium hafnate, and europium hafnate. The two capsules are planned for irradiation in the flux trap of the High Flux Isotope Reactor at two different neutron fluence levels and with a target specimen temperature of 300°C. In addition, this report shows the pre-characterization performed on the absorber material specimens. The goal of this experiment is to investigate the neutron irradiation effects on the absorber materials and characterize irradiation-induced swelling.

show abstract

Section: Thermal Analysesmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Assembly and Delivery of Capsules for Irradiation of Absorber Material Specimens in the High Flux Isotope Reactor

Coq¹,

Cetiner²,

Burns³

et al. 2019

View full text Add to dashboard Cite

show abstract

“…However, Eu will not be used in a reactor in the metallic state since the metal is extremely reactive toward water and oxygen. Therefore, ceramics or metal matrix composites (MMCs), such as europium oxide (Eu 2 O 3 ) pellets and Eu 2 O 3 -HfO 2 /ZrO 2 , are selected as control rod materials [ 10 , 11 , 12 , 13 ]. Ceramic materials have low thermal conductivity and produce thermal stress at high temperatures, leading to material failure.…”

Section: Introductionmentioning

confidence: 99%

Microstructure and Mechanical Properties of Ni-20Cr-Eu2O3 Composites Prepared by Vacuum Hot Pressing

Zhou

Yue

et al. 2023

Materials

View full text Add to dashboard Cite

Ni-20Cr-Eu2O3 composites were designed as new control rod materials and were synthesized from Ni, Cr, and Eu2O3 mixture powders via ball milling and vacuum hot pressing. During ball milling, Eu2O3 was fined, nano-crystallized, amorphized, and then dissolved into matrix. The effect of Eu2O3 content on the microstructure and mechanics was researched, and the corresponding mechanism was discussed. The relative densities, grain sizes, and microhardness increased when Eu2O3 content increased. According to the TEM observations, Eu2O3 particles showed a semi-coherent relationship with the matrix. The results of mechanical property testing showed that the ultimate tensile strength, yield strength, and elongation decreased with the Eu2O3 content increased. The maximum ultimate tensile strength, yield strength, and elongation were 741 MPa, 662 MPa, and 4%, respectively, with a 5 wt.% Eu2O3 addition. The experimental strengths were well matched with the theoretical values calculated by the strengthening mechanisms indicating that this method was highly effective for predicting the mechanical properties of Ni-20Cr-Eu2O3 composites.

show abstract

Design and Thermal Analysis for Irradiation of Absorber Material Specimens in the High Flux Isotope Reactor

Cited by 2 publications

References 4 publications

Assembly and Delivery of Capsules for Irradiation of Absorber Material Specimens in the High Flux Isotope Reactor

Assembly and Delivery of Capsules for Irradiation of Absorber Material Specimens in the High Flux Isotope Reactor

Microstructure and Mechanical Properties of Ni-20Cr-Eu2O3 Composites Prepared by Vacuum Hot Pressing

Contact Info

Product

Resources

About