Behavior of spent nuclear fuel and storage system components in dry interim storage.

Johnson, A.B.; Gilbert, E.R.; Guenther, R.J.

doi:10.2172/6883221

Cited by 14 publications

(37 citation statements)

References 19 publications

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“…elsewhere (Woodley, 1983;Johnson et al, 1983). for the present purposes, the following representative dimensions are assumed: smaller fraction of hydrogen during corrosion than does Zircaloy-2, but both have similar corrosion behavior).…”

Section: Baselines and Assumptionsmentioning

confidence: 99%

“…Johnson et al (1983) and Johnson and Gilbert (1983) report that no known cases have occurred either during actual pool storaqe or in dry storage investigations. The events are rare, even for fuel assemblies that have resided in a nuclear reactor for 16 to 17 years and have experienced operatinq conditions for 12 years Hi 1 lner, 1980;Mayman 1978).…”

Section: Stress-corrosion Cracking (Scc)mentioning

confidence: 99%

“…Internal pressures due to fission gas release in the fuel rods. Miller uses an extremely conservative 50% release, a figure four to five times higher than that used by Johnson and Gilbert (1983). Blackburn et al (1978) cite 20% as the maximum fission gas release in GESSAR-251 (1975) for the highest design power density rod.…”

Section: (Of Course Thismentioning

confidence: 99%

“…The following analysis was conducted to establish that the hydrogen Johnson, Gilbert, and Guenther (1983) reported that the hydrogen content does not exceed 400 ppm (the value mentioned above) in the repository case. content of spent fuel claddings ranges from 80 to 150 ppm.…”

Section: Simpson Ibid)mentioning

confidence: 99%

“…The later paper by Johnson, Gilbert, and Guenther (1983) gives maximum internal pressures in the PWR and BWR pins o f 2000 and 450 psi, giving corresponding maximum hoop stresses of 16,000 (PWR) and 3800 psi (BWR).…”

mentioning

confidence: 96%

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Potential corrosion and degradation mechanisms of Zircaloy cladding on spent nuclear fuel in a tuff repository

Rothman¹

1984

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Section: Baselines and Assumptionsmentioning

confidence: 99%

Section: Stress-corrosion Cracking (Scc)mentioning

confidence: 99%

Section: (Of Course Thismentioning

confidence: 99%

Section: Simpson Ibid)mentioning

confidence: 99%

mentioning

confidence: 96%

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Potential corrosion and degradation mechanisms of Zircaloy cladding on spent nuclear fuel in a tuff repository

Rothman¹

1984

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The effect of coupled wear and creep during grid-to-rod fretting

Wang

et al. 2017

Nuclear Engineering and Design

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The initial stages of grid-to-rod fretting (GTRF) is associatedwith stress-relaxation. Both creep and wear contribute to this process. These mechanisms act in concert, and are influenced by each other. The development of a strategy to couple creep and wear is important for the numerical modeling of gap formation in a pressurized-water reactor(PWR). However, thecharacteristic time scales for the two processes are very different, which can cause numerical problems. In this paper, an approach is presented to develop reasonably efficient, yet accurate,models that couple the two processes. This approach is used for a numerical analysis of gap formationduring grid-to-rod fretting. In this analysis, the effects of wear are integrated with the effects of creep relaxation, providing insight into the relative roles of the two mechanisms in this particular application.During the early stages of gap formation, the fluid-induced excitation forces are not large enough to cause macroscopic slip and wear across the entire interface. As a result, creep, rather than wear, is the dominant mechanism that dictates the evolution of the contact stress. Creep contributes to stress relaxation both through the creep-down of the cladding onto the fuel, and by local stress relaxation at the contacts. Although localized wear always occurs at the edge of the contacts, the effects are so small that this can be considered to be an incubation period for wear. Eventually, the contact force relaxes to such an extent that slip occurs over the entire contact between the pin and cladding, and wear becomes the dominant relaxation mechanism. The simulations demonstrating these concepts explored different pressure fluctuations, friction coefficients, wear coefficients, and initial interference, to show how these different parameters affect the wear profile and the time at whichcontact is lost between the grid and cladding.

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