Analysis of a small break loss-of-coolant accident of pressurized water reactor by APROS

A. Al-Falahi; Markku Hänninen; Kari Porkholm

Analysis of a small break loss-of-coolant accident of pressurized water reactor by APROS

A. Al-Falahi, Markku Hänninen, Kari Porkholm

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

Abstract

The purpose of this paper is to study the capability of APROS (Advanced PROcess Simulator) code to simulate the real plant thermal-hydraulic transient of a Small Break Loss-Of-Coolant Accident (SBLOCA) of Loss-Of-Fluid Test (LOFT) facility. The LOFT is a scaled model of a Pressurized Water Reactor (PWR). This work is a part of a larger validation of the APROS thermal-hydraulic models. The results of SBLOCA transient calculated by APROS showed a reasonable agreement with the measured data.

Original language	English
Title of host publication	Proceedings of the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7
Place of Publication	Washington, D.C.
Publisher	U.S. Nuclear Regulatory Commission
Pages	2263-2279
Volume	3
Publication status	Published - 1995
MoE publication type	A4 Article in a conference publication
Event	7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7 - Saratoga Springs, United States Duration: 10 Sept 1995 → 15 Sept 1995

Publication series

Series	NUREG/CP
Number	0142
ISSN	0270-6482

Conference

Conference	7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7
Country/Territory	United States
City	Saratoga Springs
Period	10/09/95 → 15/09/95

Cite this

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title = "Analysis of a small break loss-of-coolant accident of pressurized water reactor by APROS",

abstract = "The purpose of this paper is to study the capability of APROS (Advanced PROcess Simulator) code to simulate the real plant thermal-hydraulic transient of a Small Break Loss-Of-Coolant Accident (SBLOCA) of Loss-Of-Fluid Test (LOFT) facility. The LOFT is a scaled model of a Pressurized Water Reactor (PWR). This work is a part of a larger validation of the APROS thermal-hydraulic models. The results of SBLOCA transient calculated by APROS showed a reasonable agreement with the measured data.",

author = "A. Al-Falahi and Markku H{\"a}nninen and Kari Porkholm",

note = "Project code: 5423; 7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7 ; Conference date: 10-09-1995 Through 15-09-1995",

year = "1995",

language = "English",

volume = "3",

series = "NUREG/CP",

publisher = "U.S. Nuclear Regulatory Commission",

number = "0142",

pages = "2263--2279",

booktitle = "Proceedings of the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7",

address = "United States",

}

Al-Falahi, A, Hänninen, M & Porkholm, K 1995, Analysis of a small break loss-of-coolant accident of pressurized water reactor by APROS. in Proceedings of the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7. vol. 3, U.S. Nuclear Regulatory Commission, Washington, D.C., NUREG/CP, no. 0142, pp. 2263-2279, 7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7, Saratoga Springs, New York, United States, 10/09/95.

Analysis of a small break loss-of-coolant accident of pressurized water reactor by APROS. / Al-Falahi, A.; Hänninen, Markku; Porkholm, Kari.
Proceedings of the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7. Vol. 3 Washington, D.C.: U.S. Nuclear Regulatory Commission, 1995. p. 2263-2279 (NUREG/CP; No. 0142).

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

TY - GEN

T1 - Analysis of a small break loss-of-coolant accident of pressurized water reactor by APROS

AU - Al-Falahi, A.

AU - Hänninen, Markku

AU - Porkholm, Kari

N1 - Project code: 5423

PY - 1995

Y1 - 1995

N2 - The purpose of this paper is to study the capability of APROS (Advanced PROcess Simulator) code to simulate the real plant thermal-hydraulic transient of a Small Break Loss-Of-Coolant Accident (SBLOCA) of Loss-Of-Fluid Test (LOFT) facility. The LOFT is a scaled model of a Pressurized Water Reactor (PWR). This work is a part of a larger validation of the APROS thermal-hydraulic models. The results of SBLOCA transient calculated by APROS showed a reasonable agreement with the measured data.

AB - The purpose of this paper is to study the capability of APROS (Advanced PROcess Simulator) code to simulate the real plant thermal-hydraulic transient of a Small Break Loss-Of-Coolant Accident (SBLOCA) of Loss-Of-Fluid Test (LOFT) facility. The LOFT is a scaled model of a Pressurized Water Reactor (PWR). This work is a part of a larger validation of the APROS thermal-hydraulic models. The results of SBLOCA transient calculated by APROS showed a reasonable agreement with the measured data.

M3 - Conference article in proceedings

VL - 3

T3 - NUREG/CP

SP - 2263

EP - 2279

BT - Proceedings of the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7

PB - U.S. Nuclear Regulatory Commission

CY - Washington, D.C.

T2 - 7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7

Y2 - 10 September 1995 through 15 September 1995

ER -

Analysis of a small break loss-of-coolant accident of pressurized water reactor by APROS

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