Assessment of RELAP5/MOD2 against a turbine trip from 100% power in the Vandellos II nuclear power plant

Technical Report · Tue Jun 01 00:00:00 EDT 1993

OSTI ID:10163354

Llopis, C ^[1]; Perez, J; Mendizabal, R ^[2]

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1. Asociacion Nuclear Vandellos, Barcelona (ES)
2. Consejo de Seguridad Nuclear, Madrid (ES)

An assessment of RELAP5/MOD2 cycle 36.04 against a turbine trip from 100% power in the Vandellos II NPP (Spain) is presented. The work is inscribed in the framework of the Spanish contribution to ICAP Project. The model used in the simulation consists of a single loop, a steam generator and a steam line up to the steam header all of them enlarged on a scale of 3:1; and full-scaled reactor vessel and pressurizer. The results of calculations have been in reasonable agreement with plant measurements. An additional study has been performed to check the ability of a model in which all the plant components are full-scaled to reproduce the transient. A second study has been performed using the Homogeneous Equilibrium Model in the pressurizer, trying to elucidate the influence of the velocity slip in the primary depressurization rate.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research; Asociacion Nuclear de Vandellos, Barcelona (Spain); Consejo de Seguridad Nuclear, Madrid (Spain)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• OSTI ID: 10163354
• Report Number(s): NUREG/IA-0108; ICSP-V2-R100-R; ON: TI93015385; TRN: 93:001646
• Resource Relation: Other Information: PBD: Jun 1993
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
VANDELLOS-2 REACTOR
TRANSIENTS
R CODES
EVALUATION
SPAIN
CDC COMPUTERS
STEAM TURBINES
COMPUTERIZED SIMULATION
INTERNATIONAL COOPERATION
EXPERIMENTAL DATA
US NRC
REACTOR VESSELS
210200
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED