Reactor physics and dynamics (READY)

Validation of TRAB-3D

Antti Daavittila, Hanna Räty

Research output: Chapter in Book/Report/Conference proceedingChapter or book articleProfessional

Abstract

TRAB-3D is a reactor dynamics code with three-dimensional neutronics coupled to core and circuit thermal-hydraulics. The code, entirely developed at VTT, can be used in transient and accident analyses of boiling (BWR) and pressurized water (PWR) reactors with rectangular fuel bundle geometry. The validation history of TRAB-3D includes calculation of international benchmark exercises, as well as comparisons with measured data from real plant transients. The most recent validation case is a load rejection test performed at the Olkiluoto 1 nuclear power plant in 1998 in connection with the power uprating project. The fact that there is local power measurement data available from this test makes it a suitable case for three-dimensional core model validation. The agreement between the results of the TRAB-3D calculation and the measurements is very good.
Original languageEnglish
Title of host publicationFINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002
Subtitle of host publicationFinal Report
Place of PublicationEspoo
PublisherVTT Technical Research Centre of Finland
Pages127-133
ISBN (Electronic)951-38-6086-8
ISBN (Print)951-38-6085-X
Publication statusPublished - 2002
MoE publication typeNot Eligible

Publication series

NameVTT Tiedotteita - Research Notes
PublisherVTT
Number2164
ISSN (Print)1235-0605
ISSN (Electronic)1455-0865

Fingerprint

Physics
Pressurized water reactors
Boiling liquids
Nuclear power plants
Accidents
Hydraulics
Geometry
Networks (circuits)
Hot Temperature

Cite this

Daavittila, A., & Räty, H. (2002). Reactor physics and dynamics (READY): Validation of TRAB-3D. In FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002: Final Report (pp. 127-133). Espoo: VTT Technical Research Centre of Finland. VTT Tiedotteita - Research Notes, No. 2164
Daavittila, Antti ; Räty, Hanna. / Reactor physics and dynamics (READY) : Validation of TRAB-3D. FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002: Final Report. Espoo : VTT Technical Research Centre of Finland, 2002. pp. 127-133 (VTT Tiedotteita - Research Notes; No. 2164).
@inbook{64cfc95a92984a778ac6648234139ac7,
title = "Reactor physics and dynamics (READY): Validation of TRAB-3D",
abstract = "TRAB-3D is a reactor dynamics code with three-dimensional neutronics coupled to core and circuit thermal-hydraulics. The code, entirely developed at VTT, can be used in transient and accident analyses of boiling (BWR) and pressurized water (PWR) reactors with rectangular fuel bundle geometry. The validation history of TRAB-3D includes calculation of international benchmark exercises, as well as comparisons with measured data from real plant transients. The most recent validation case is a load rejection test performed at the Olkiluoto 1 nuclear power plant in 1998 in connection with the power uprating project. The fact that there is local power measurement data available from this test makes it a suitable case for three-dimensional core model validation. The agreement between the results of the TRAB-3D calculation and the measurements is very good.",
author = "Antti Daavittila and Hanna R{\"a}ty",
year = "2002",
language = "English",
isbn = "951-38-6085-X",
series = "VTT Tiedotteita - Research Notes",
publisher = "VTT Technical Research Centre of Finland",
number = "2164",
pages = "127--133",
booktitle = "FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002",
address = "Finland",

}

Daavittila, A & Räty, H 2002, Reactor physics and dynamics (READY): Validation of TRAB-3D. in FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002: Final Report. VTT Technical Research Centre of Finland, Espoo, VTT Tiedotteita - Research Notes, no. 2164, pp. 127-133.

Reactor physics and dynamics (READY) : Validation of TRAB-3D. / Daavittila, Antti; Räty, Hanna.

FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002: Final Report. Espoo : VTT Technical Research Centre of Finland, 2002. p. 127-133 (VTT Tiedotteita - Research Notes; No. 2164).

Research output: Chapter in Book/Report/Conference proceedingChapter or book articleProfessional

TY - CHAP

T1 - Reactor physics and dynamics (READY)

T2 - Validation of TRAB-3D

AU - Daavittila, Antti

AU - Räty, Hanna

PY - 2002

Y1 - 2002

N2 - TRAB-3D is a reactor dynamics code with three-dimensional neutronics coupled to core and circuit thermal-hydraulics. The code, entirely developed at VTT, can be used in transient and accident analyses of boiling (BWR) and pressurized water (PWR) reactors with rectangular fuel bundle geometry. The validation history of TRAB-3D includes calculation of international benchmark exercises, as well as comparisons with measured data from real plant transients. The most recent validation case is a load rejection test performed at the Olkiluoto 1 nuclear power plant in 1998 in connection with the power uprating project. The fact that there is local power measurement data available from this test makes it a suitable case for three-dimensional core model validation. The agreement between the results of the TRAB-3D calculation and the measurements is very good.

AB - TRAB-3D is a reactor dynamics code with three-dimensional neutronics coupled to core and circuit thermal-hydraulics. The code, entirely developed at VTT, can be used in transient and accident analyses of boiling (BWR) and pressurized water (PWR) reactors with rectangular fuel bundle geometry. The validation history of TRAB-3D includes calculation of international benchmark exercises, as well as comparisons with measured data from real plant transients. The most recent validation case is a load rejection test performed at the Olkiluoto 1 nuclear power plant in 1998 in connection with the power uprating project. The fact that there is local power measurement data available from this test makes it a suitable case for three-dimensional core model validation. The agreement between the results of the TRAB-3D calculation and the measurements is very good.

M3 - Chapter or book article

SN - 951-38-6085-X

T3 - VTT Tiedotteita - Research Notes

SP - 127

EP - 133

BT - FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002

PB - VTT Technical Research Centre of Finland

CY - Espoo

ER -

Daavittila A, Räty H. Reactor physics and dynamics (READY): Validation of TRAB-3D. In FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002: Final Report. Espoo: VTT Technical Research Centre of Finland. 2002. p. 127-133. (VTT Tiedotteita - Research Notes; No. 2164).