Materials Selection for the HFIR Cold Neutron Source

Farrell, K.

doi:10.2172/786477

Cited by 5 publications

(5 citation statements)

References 16 publications

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“…It was highlighted in [3] that both the thermal and fast neutrons play independent and important roles leading to microstructural damage and corresponding property changes. A very high TFR, ranging from 80 to 500, could explain the observed craze-cracking in AG3-NET alloy (Al-3% Mg) beam tubes in the Reactor Haut Flux (RHF) at Grenoble [23]. Lijbrink et al [12] pointed out that fast neutron flux reduces the effectiveness of the Si precipitation hardening process.…”

Section: Effect Of Thermal-to-fast Flux Ratio (Tfr)mentioning

confidence: 99%

Neutron Irradiation Effects in 5xxx and 6xxx Series Aluminum Alloys: A Literature Review

Kolluri¹

2016

Radiation Effects in Materials

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A literature review on highly irradiated 5xxx and 6xxx series Al alloys is conducted to understand the expected changes in mechanical properties of high flux reactor (HFR) vessel material in relation with microstructural aspects beyond the current surveillance data to support the HFR Surveillance Program (SURP). It was found that the irradiation swelling in 5xxx series alloys is not a crucial degradation mechanism. Dislocation damage is expected to reach a saturation limit in both 5xxx and 6xxx series alloys at relatively low fast-fluence values (<2 × 10 26 n/m 2). The damage caused by precipitation of transmutation Si is found to be the dominant mechanism affecting the fracture toughness properties of irradiated 5xxx and 6xxx series Al alloys at high thermal fluence values. Tensile and fracture toughness data collected from the literature up to very high thermal fluences are analyzed in comparison with the available HFR surveillance data to predict the behavior of the HFR vessel material beyond current surveillance data. The observed changes in mechanical properties are classified into four different regimes. The contribution of various irradiation damage mechanisms, namely the displacement damage and transmutation damage, to the evolution of microstructure and mechanical properties is discussed in all four regimes for 5xxx and 6xxx series alloys.

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Section: Effect Of Thermal-to-fast Flux Ratio (Tfr)mentioning

confidence: 99%

Neutron Irradiation Effects in 5xxx and 6xxx Series Aluminum Alloys: A Literature Review

Kolluri¹

2016

Radiation Effects in Materials

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“…84 For 6061Al in particular, see Farrell. 85 Strengthening and loss of ductility are demonstrated best in tensile properties. In Figure 12 we can directly compare the changes in strength and ductility of different alloys irradiated and tested under the same conditions.…”

Section: Mechanical Propertiesmentioning

confidence: 99%

“…Details are available in Farrell. 85 Creep can lead to failure if the load is continuously applied. Strain from stress relaxation ceases once the load is relaxed.…”

Section: Radiation Softening Creep and Stress Relaxationmentioning

confidence: 99%

Performance of Aluminum in Research Reactors

Farrell

2012

Comprehensive Nuclear Materials

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“…We introduce another Al alloy (Al5083) and ternary Ag-In-Cd alloy. This Al alloy is not a heat-treated material, which dose not require the heat treatment to recover the mechanical strength after HIPing, however, it gives a short lifetime for the neutron irradiation as compared with the Al6061-T6 [6]. On the other hand, we found the Be reflector E n =100 meV necessary Cd composition in the Ag single phase of the ternary AIC to satisfy the required lifetime of the moderator by the neutronic calculation.…”

Section: Introductionmentioning

confidence: 77%

“…From a point of view of heat removal and corrosion protection, an AIC plate with the thickness of 3 mm has to be bonded between two plates of the Al alloy, which is the structural material of a moderator or reflector. Especially, from the neutron irradiation point of view, an Al6061-T6 is recommended as a structural material of the moderator [6]. We adopted HIP (Hot Isostatic Pressing) method to obtain the bonding material between the Al6061-T6 and the AIC.…”

Section: Introductionmentioning

confidence: 99%