Application of RELAP5/MOD2 to Loviisa Nuclear Power Plant Overcooling Transients

Autor:	Harri Tuomisto, Vesa Yrjölä, Heikki Kantee
Rok vydání:	1990
Předmět:	Nuclear and High Energy Physics Source code Computer science media_common.quotation_subject Nuclear engineering Condensed Matter Physics law.invention Nuclear Energy and Engineering law Pressurizer Nuclear power plant Steam line Safety valve Leakage (electronics) media_common
Zdroj:	Kantee, H, Tuomisto, H & Yrjölä, V 1990, ' Application of RELAP5/MOD2 to Loviisa nuclear power plant overcooling transients ', Nuclear Technology, vol. 90, no. 3, pp. 308-315 . https://doi.org/10.13182/NT90-A34396
ISSN:	1943-7471 0029-5450
DOI:	10.13182/nt90-a34396
Popis:	The RELAP5/MOD2 computer code has been extensively utilized in calculation of thermal-hydraulic sequences concerning the pressurized thermal shock safety issue in the Loviisa 1 nuclear power plant. The cases analyzed feature stuck-open pressurizer safety valve sequences, small hot-leg breaks, steam line breaks, and, in one case, a primary-secondary leakage. The main purpose of these analyses is to validate and compare the results from the full-scale Loviisa training simulator analyses.The RELAP5 model is made to the detail allowed by the computer. It includes a description of primary and secondary circuits as well as modeling of the emergency core cooling and control systems.Single-phase thermal stratification and mixing are essential phenomena when pressurized thermal shock sequences are analyzed. The capabilities of the large system analysis code to predict these phenomena in the reactor circuit are discussed
Databáze:	OpenAIRE
Externí odkaz:	https://explore.openaire.eu/search/publication?articleId=doi_dedup___::5848c68050bec38f7ebc6d01270f676e https://doi.org/10.13182/nt90-a34396 Zobrazit plný text záznamu