Advanced oxidation-resistant iron-based alloys for LWR fuel cladding

Terrani, Kurt A.; Zinkle, S.J.; Snead, Lance Lewis

doi:10.1016/j.jnucmat.2013.06.041

Cited by 495 publications

(257 citation statements)

References 84 publications

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“…The reference case chosen was from a standard PWR 17×17 fuel bundle [10] with 4.9% enriched urania (UO 2 ) pellets. The density of the UO 2 pellet is set at 96% of theoretical density, yielding 10.47 g/cm 3 . The pitch-to-diameter ratio (P/D) for all the cases is fixed at 1.326.…”

Section: Methodsology and Input Parametersmentioning

confidence: 99%

“…This implies that any evolution in performance characteristics of the cladding will be dominated by radiation effects as opposed chemical alterations. The discussion on irradiation effects and operational performance of these alloys is well beyond the scope of this manuscript and is discussed in detail elsewhere [3]. Figure 7 shows the total plutonium inventory in the fuel pellets for the reference rod geometry with various cladding materials.…”

Section: Isotopic Evolution In the Claddingmentioning

confidence: 99%

“…This is done by compromising coolability in the core and deposition of a large amount of enthalpy (oxidation) in addition to what is deposited by decay heat [2]. Given this understanding, an international effort is under way to examine alternate fuel cladding concepts that exhibit slower oxidation kinetics in high-temperature steam environments when compared to zirconium alloys [3][4][5].…”

Section: Introductionmentioning

confidence: 99%

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Neutronic analysis of candidate accident-tolerant iron alloy cladding concepts

George¹,

Terrani²,

Powers³

2013

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Section: Methodsology and Input Parametersmentioning

confidence: 99%

Section: Isotopic Evolution In the Claddingmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Neutronic analysis of candidate accident-tolerant iron alloy cladding concepts

George¹,

Terrani²,

Powers³

2013

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“…At the moment, alloys of the Fe-Cr-Al system are being studied in the world for their application as fuel rod cladding for nuclear reactors [1][2][3]. The chromium content in these steels ranges from 10 to 20 wt.%, the aluminum content is from 3 to 5 wt.% [3].…”

Section: Introductionmentioning

confidence: 99%

Corrosion Resistance of Fe-Cr-Al-Si Alloys with Low Chromium Content

Тарасов¹,

Savelyev²,

Shornikov³

2018

Kms

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Within the framework of this work, alloys with a chromium content of 5 to14 wt%, aluminum from 0 to 4 wt% and silicon from 0 to 4 wt%. The samples were tested for resistance to oxidation with calm dry air (800 ∘ C, 0.1 MPa) for 60 hours; in highparameter water (350 ∘ C, 16 MPa), for 300 hours; in steam (400 ∘ C, 10 MPa), for 72 hours and superheated steam (1100 ∘ C, 0.1 MPa) for 1 hour.The compositions most resistant to corrosion under the specified conditions were determined, and the existence of a synergistic effect of silicon and aluminum as alloying elements of iron alloys was confirmed.

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“…Despite the stainless steel economics penalty, the main advantage of using this material as cladding comes from the reduction of the probability of the violent oxidation reaction that occurs with zirconium-based alloys at high temperatures, as it has occurred in the Fukushima Daiichi accident [3]. As a consequence of this, iron-based alloys once again can be considered as a good option to replace zirconium-based alloys as cladding material improving the safety under accident scenarios [4]. Considering the previous good experience of AISI 348 as cladding, this material could be again applied to replace zirconium-based alloys as PWR fuel cladding.…”

Section: Introductionmentioning

confidence: 99%

Assessment of stainless steel 348 fuel rod performance against literature available data using TRANSURANUS code

Giovedi

Cherubini

Abe

et al. 2016

EPJ Nuclear Sci. Technol.

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Abstract. Early pressurized water reactors were originally designed to operate using stainless steel as cladding material, but during their lifetime this material was replaced by zirconium-based alloys. However, after the Fukushima Daiichi accident, the problems related to the zirconium-based alloys due to the hydrogen production and explosion under severe accident brought the importance to assess different materials. In this sense, initiatives as ATF (Accident Tolerant Fuel) program are considering different material as fuel cladding and, one candidate is iron-based alloy. In order to assess the fuel performance of fuel rods manufactured using iron-based alloy as cladding material, it was necessary to select a specific stainless steel (type 348) and modify properly conventional fuel performance codes developed in the last decades. Then, 348 stainless steel mechanical and physics properties were introduced in the TRANSURANUS code. The aim of this paper is to present the obtained results concerning the verification of the modified TRANSURANUS code version against data collected from the open literature, related to reactors which operated using stainless steel as cladding. Considering that some data were not available, some assumptions had to be made. Important differences related to the conventional fuel rods were taken into account. Obtained results regarding the cladding behavior are in agreement with available information. This constitutes an evidence of the modified TRANSURANUS code capabilities to perform fuel rod investigation of fuel rods manufactured using 348 stainless steel as cladding material. IntroductionThe available data shows that the steady state performance of steel cladding in the first PWR was considered excellent [1,2]. The material used in the early PWR was mainly AISI 304 (12% cold worked). Nonetheless, some reactors operated using annealed AISI 348, which presents a better corrosion resistance due to the addition of niobium and tantalum in its composition.The substitution of stainless steel by zircaloy as cladding material was due to the lower absorption for thermal neutrons of the zirconium-based alloys which enables to operate with lower enrichment cost. Despite the stainless steel economics penalty, the main advantage of using this material as cladding comes from the reduction of the probability of the violent oxidation reaction that occurs with zirconium-based alloys at high temperatures, as it has occurred in the Fukushima Daiichi accident [3]. As a consequence of this, iron-based alloys once again can be considered as a good option to replace zirconium-based alloys as cladding material improving the safety under accident scenarios [4]. Considering the previous good experience of AISI 348 as cladding, this material could be again applied to replace zirconium-based alloys as PWR fuel cladding.In order to evaluate the fuel performance of fuel rods using AISI 348 as cladding, it is necessary to modify the current fuel performance codes to insert correlations and properties of this materi...

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Advanced oxidation-resistant iron-based alloys for LWR fuel cladding

Cited by 495 publications

References 84 publications

Neutronic analysis of candidate accident-tolerant iron alloy cladding concepts

Neutronic analysis of candidate accident-tolerant iron alloy cladding concepts

Corrosion Resistance of Fe-Cr-Al-Si Alloys with Low Chromium Content

Assessment of stainless steel 348 fuel rod performance against literature available data using TRANSURANUS code

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