Analysis of the operator action and the single failure criteria in a SGTR sequence using best estimate assumptions with TRACE 5.0

Jiménez Varas, Gonzalo; Queral Salazar, José Cesar; Rebollo, M.J.; Martínez-Murillo Méndez, Juan Carlos y López Alonso, E. (2013). Analysis of the operator action and the single failure criteria in a SGTR sequence using best estimate assumptions with TRACE 5.0. "Annals of Nuclear Energy", v. 58 ; pp. 161-177. ISSN 0306-4549. https://doi.org/10.1016/j.anucene.2013.02.023.

Descripción

Título: Analysis of the operator action and the single failure criteria in a SGTR sequence using best estimate assumptions with TRACE 5.0
Autor/es:
  • Jiménez Varas, Gonzalo
  • Queral Salazar, José Cesar
  • Rebollo, M.J.
  • Martínez-Murillo Méndez, Juan Carlos
  • López Alonso, E.
Tipo de Documento: Artículo
Título de Revista/Publicación: Annals of Nuclear Energy
Fecha: Agosto 2013
Volumen: 58
Materias:
Palabras Clave Informales: SGTR; TRACE; RADTRAD; FSAR; Offsite dose; MTO
Escuela: E.T.S.I. Industriales (UPM)
Departamento: Ingeniería Energética
Licencias Creative Commons: Reconocimiento - Sin obra derivada - No comercial

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Resumen

Steam Generator Tube Rupture (SGTR) sequences in Pressurized Water Reactors are known to be one of the most demanding transients for the operating crew. SGTR are a special kind of transient as they could lead to radiological releases without core damage or containment failure, as they can constitute a direct path from the reactor coolant system to the environment. The first methodology used to perform the Deterministic Safety Analysis (DSA) of a SGTR did not credit the operator action for the first 30 min of the transient, assuming that the operating crew was able to stop the primary to secondary leakage within that period of time. However, the different real SGTR accident cases happened in the USA and over the world demonstrated that the operators usually take more than 30 min to stop the leakage in actual sequences. Some methodologies were raised to overcome that fact, considering operator actions from the beginning of the transient, as it is done in Probabilistic Safety Analysis. This paper presents the results of comparing different assumptions regarding the single failure criteria and the operator action taken from the most common methodologies included in the different Deterministic Safety Analysis. One single failure criteria that has not been analysed previously in the literature is proposed and analysed in this paper too. The comparison is done with a PWR Westinghouse three loop model in TRACE code (Almaraz NPP) with best estimate assumptions but including deterministic hypothesis such as single failure criteria or loss of offsite power. The behaviour of the reactor is quite diverse depending on the different assumptions made regarding the operator actions. On the other hand, although there are high conservatisms included in the hypothesis, as the single failure criteria, all the results are quite far from the regulatory limits. In addition, some improvements to the Emergency Operating Procedures to minimize the offsite release from the damaged SG in case of a SGTR are outlined taking into account the offsite dose sensitivity results.

Más información

ID de Registro: 25740
Identificador DC: http://oa.upm.es/25740/
Identificador OAI: oai:oa.upm.es:25740
Identificador DOI: 10.1016/j.anucene.2013.02.023
URL Oficial: http://www.sciencedirect.com/science/article/pii/S0306454913001114
Depositado por: Memoria Investigacion
Depositado el: 26 Feb 2015 16:06
Ultima Modificación: 01 Mar 2017 16:36
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