Evaluation of reflooding effects on an overheated BWR core in a small steam line break accident using MAAP, MELCOR and SCDAP/RELAP5 computer codes

Ilona Lindholm; Esko Pekkarinen; Heikki Sjövall

Evaluation of reflooding effects on an overheated BWR core in a small steam line break accident using MAAP, MELCOR and SCDAP/RELAP5 computer codes

Ilona Lindholm, Esko Pekkarinen, Heikki Sjövall

Teollisuuden Voima Oyj

Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review

Original language	English
Title of host publication	International Conference on New Trends in Nuclear System Thermohydraulics
Subtitle of host publication	Thermohydraulics of Containment and Severe Accidents
Editors	Francesco Oriolo, Piero Vigni
Place of Publication	Pisa
Publisher	University of Pisa
Pages	233-243
Volume	2
Publication status	Published - 1994
MoE publication type	A4 Article in a conference publication
Event	International Conference on New Trends in Nuclear System Thermohydraulics - Pisa, Italy Duration: 30 May 1994 → 2 Jun 1994

Conference

Conference	International Conference on New Trends in Nuclear System Thermohydraulics
Country/Territory	Italy
City	Pisa
Period	30/05/94 → 2/06/94

Cite this

Lindholm, I., Pekkarinen, E., & Sjövall, H. (1994). Evaluation of reflooding effects on an overheated BWR core in a small steam line break accident using MAAP, MELCOR and SCDAP/RELAP5 computer codes. In F. Oriolo, & P. Vigni (Eds.), International Conference on New Trends in Nuclear System Thermohydraulics: Thermohydraulics of Containment and Severe Accidents (Vol. 2, pp. 233-243). University of Pisa.

Lindholm, Ilona ; Pekkarinen, Esko ; Sjövall, Heikki. / Evaluation of reflooding effects on an overheated BWR core in a small steam line break accident using MAAP, MELCOR and SCDAP/RELAP5 computer codes. International Conference on New Trends in Nuclear System Thermohydraulics: Thermohydraulics of Containment and Severe Accidents. editor / Francesco Oriolo ; Piero Vigni. Vol. 2 Pisa : University of Pisa, 1994. pp. 233-243

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title = "Evaluation of reflooding effects on an overheated BWR core in a small steam line break accident using MAAP, MELCOR and SCDAP/RELAP5 computer codes",

author = "Ilona Lindholm and Esko Pekkarinen and Heikki Sj{\"o}vall",

note = "HUO: T{\"A}M{\"A} KUULUU LUOKKAAN A: TIETEELLISET JULKAISUT Project code: ENE44243; International Conference on New Trends in Nuclear System Thermohydraulics ; Conference date: 30-05-1994 Through 02-06-1994",

year = "1994",

language = "English",

volume = "2",

pages = "233--243",

editor = "Francesco Oriolo and Piero Vigni",

booktitle = "International Conference on New Trends in Nuclear System Thermohydraulics",

publisher = "University of Pisa",

address = "Italy",

}

Lindholm, I, Pekkarinen, E & Sjövall, H 1994, Evaluation of reflooding effects on an overheated BWR core in a small steam line break accident using MAAP, MELCOR and SCDAP/RELAP5 computer codes. in F Oriolo & P Vigni (eds), International Conference on New Trends in Nuclear System Thermohydraulics: Thermohydraulics of Containment and Severe Accidents. vol. 2, University of Pisa, Pisa, pp. 233-243, International Conference on New Trends in Nuclear System Thermohydraulics, Pisa, Italy, 30/05/94.

Evaluation of reflooding effects on an overheated BWR core in a small steam line break accident using MAAP, MELCOR and SCDAP/RELAP5 computer codes. / Lindholm, Ilona; Pekkarinen, Esko; Sjövall, Heikki.
International Conference on New Trends in Nuclear System Thermohydraulics: Thermohydraulics of Containment and Severe Accidents. ed. / Francesco Oriolo; Piero Vigni. Vol. 2 Pisa: University of Pisa, 1994. p. 233-243.

Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review

TY - GEN

T1 - Evaluation of reflooding effects on an overheated BWR core in a small steam line break accident using MAAP, MELCOR and SCDAP/RELAP5 computer codes

AU - Lindholm, Ilona

AU - Pekkarinen, Esko

AU - Sjövall, Heikki

N1 - HUO: TÄMÄ KUULUU LUOKKAAN A: TIETEELLISET JULKAISUT Project code: ENE44243

PY - 1994

Y1 - 1994

M3 - Conference article in proceedings

VL - 2

SP - 233

EP - 243

BT - International Conference on New Trends in Nuclear System Thermohydraulics

A2 - Oriolo, Francesco

A2 - Vigni, Piero

PB - University of Pisa

CY - Pisa

T2 - International Conference on New Trends in Nuclear System Thermohydraulics

Y2 - 30 May 1994 through 2 June 1994

ER -

Lindholm I, Pekkarinen E, Sjövall H. Evaluation of reflooding effects on an overheated BWR core in a small steam line break accident using MAAP, MELCOR and SCDAP/RELAP5 computer codes. In Oriolo F, Vigni P, editors, International Conference on New Trends in Nuclear System Thermohydraulics: Thermohydraulics of Containment and Severe Accidents. Vol. 2. Pisa: University of Pisa. 1994. p. 233-243