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The life and the contribution of B. R. Sehgal, G. Yadigaroglu and G. Hewitt: Remembrance statements

Publikováno v: Nuclear Engineering and Design. 354:110252

Foreword Solicited or voluntary statements have been collected by the Editor of the Special Issue (SI). Tributes to Sehgal, Yadigaroglu and Hewitt are reported in the alphabetical order of those who originated them. The concise tributes by N. Todreas

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::d3ba1ebe59160738ecf815b4ed5ff07c
https://doi.org/10.1016/j.nucengdes.2019.110252

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Significance of fluid-structure interaction phenomena for containment response to ex-vessel steam explosions

Autor: W Frid, A Engelbrektson, T Sundel, H Almström

Publikováno v: Nuclear Engineering and Design. 189:405-422

When studying the structural response of a containment building to ex-vessel steam explosion loads, a two-step procedure is often used. In the first step of this procedure the structures are treated as rigid and the pressure-time history generated by

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::b8fa65f16425cc20e6fdbe4181a02a7c
https://doi.org/10.1016/s0029-5493(98)00272-6

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Source Term Assessment: Method and Tool in the Acute Phase

Autor: C. Calmtorp, R. Olsson, K. Johansson, W. Frid

Publikováno v: Radiation Protection Dosimetry. 73:285-288

Early in a nuclear power plant accident there is a need to distinguish a potentially large release of Class 4 or higher on the International Nuclear Event Scale (INES) from smaller ones. The main goal is to plan off-site measures ahead of the events.

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::8545bc48aad02b7f93da5a632c6f5a2b
https://doi.org/10.1093/oxfordjournals.rpd.a032154

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Ex-vessel melt-coolant interactions in deep water pool: studies and accident management for Swedish BWRs

Autor: B.W. Spencer, W. Frid, G. Löwenhielm, James J. Sienicki, C.C. Chu

Publikováno v: Nuclear Engineering and Design. 155:159-213

In Swedish BWRs having an annular suppression pool, the lower drywell beneath the reactor vessel is flooded with water to mitigate against the effects of melt release into the drywell during a severe accident. The Thirmal-1 code has been used to anal

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::7ef05789d972c684857e8fd49e69447e
https://doi.org/10.1016/0029-5493(94)00874-x

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Severe accident recriticality analyses (SARA)

Autor: Ilona Lindholm, Jaakko Miettinen, E.K. Puska, F. Höjerup, Heikki Sjövall, W. Frid, L. Nilsson

Publikováno v: Frid, W, Höjerup, F, Lindholm, I, Miettinen, J, Nilsson, K, Puska, E K & Sjövall, H 2001, ' Severe accident recriticality analyses (SARA) ', Nuclear Engineering and Design, vol. 209, no. 1-3, pp. 97-106 . https://doi.org/10.1016/S0029-5493(01)00392-2

Recriticality in a BWR during reflooding of an overheated partly degraded core, i.e. with relocated control rods, has been studied for a total loss of electric power accident scenario. In order to assess the impact of recriticality on reactor safety,

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::eeef2c97b79ce634678df4d5388af8a2
https://cris.vtt.fi/en/publications/137b5c37-5d84-4d68-a246-c54d7ecb5714

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A comparison of world-wide uses of severe reactor accident source terms

Autor: R.Y. Lee, D. Sweet, D.A. Powers, M.L. Ang, E.J. Kersting, W. Frid, K. Soda, A. Meyer-Heine, H.G. Friederichs

The definitions of source terms to reactor containments and source terms to the environment are discussed. A comparison is made between the TID-14844 example source term and the alternative source term described in NUREG-1465. Comparisons of these so

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::2875480add9108742babf521bd342680
https://doi.org/10.2172/10188800

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