A design-phase PSA of anuclear-powered hydrogen plant


Autoria(s): Flores Flores, Alain
Data(s)

01/02/2007

Resumo

A probabilistic safety assessment (PSA) is being developed for a steam-methane reforming hydrogenproduction plant linked to a high-temperature gas-cooled nuclear reactor (HTGR). This work is based on the Japan Atomic Energy Research Institute's (JAERI) High Temperature Engineering Test Reactor (HTTR) prototype in Japan. The objective of this paper is to show how the PSA can be used for improving the design of the coupled plants. A simplified HAZOP study was performed to identify initiating events, based on existing studies. The results of the PSA show that the average frequency of an accident at this complex that could affect the population is 7 × 10−8 year−1 which is divided into the various end states. The dominant sequences are those that result in a methane explosion and occur with a frequency of 6.5 × 10−8 year−1, while the other sequences are much less frequent. The health risk presents itself if there are people in the vicinity who could be affected by the explosion. This analysis also demonstrates that an accident in one of the plants has little effect on the other. This is true given the design base distance between the plants, the fact that the reactor is underground, as well as other safety characteristics of the HTGR.

Formato

application/pdf

Identificador

http://oa.upm.es/10848/

Idioma(s)

spa

Publicador

E.T.S.I. Industriales (UPM)

Relação

http://oa.upm.es/10848/2/INVE_MEM_2007_98367.pdf

http://www.sciencedirect.com/science/article/pii/S0029549306004286

info:eu-repo/semantics/altIdentifier/doi/10.1016/j.nucengdes.2006.06.006

Direitos

http://creativecommons.org/licenses/by-nc-nd/3.0/es/

info:eu-repo/semantics/openAccess

Fonte

Nuclear Engineering and Design, ISSN 0029-5493, 2007-02, Vol. 237, No. 3

Palavras-Chave #Energía Nuclear
Tipo

info:eu-repo/semantics/article

Artículo

PeerReviewed