Advanced qualification process of ANAV NPP integral dynamic models for supporting plant operation and control-Reference-Cited by-同舟云学术

Advanced qualification process of ANAV NPP integral dynamic models for supporting plant operation and control

Published:2007-01 Issue:1 Volume:237 Page:54-63
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Reventós F.,Batet L.,Llopis C.,Pretel C.,Salvat M.,Sol I.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference14 articles.

1. Good Practices for User Effect Reduction. NEA/CSNI/R(98)22;Ashley,1998

2. Berthon, A., Petruzzi, A., Giannotti, W., D′Auria, F., Reventós, F., 2006. Consistent Code Qualification Process and Application to the LOBI test BL-44. In Working Material of IAEA Technical Meeting on: Use of a Best Estimate Approach in Licensing with Evaluation of Uncertainties.

3. IAEA, 2002. Accident Analysis for Nuclear Power Plants. Safety Report Series No. 23. International Atomic Energy Agency, Vienna.

4. Llopis, C., Pérez, J., Casals, A., Mendizábal, R., 1993a. Assessment of relap5/mod2 against a 10% load rejection transient from 75% steady state in the Vandellòs II NPP. International Agreement Report, US Nuclear Regulatory Commission Nureg/ia-109.

5. Llopis, C., Pérez, J., Mendizábal, R., 1993b. Assessment of relap5/mod2 against a turbine trip from 100% power in the Vandellòs II NPP. International Agreement Report, US Nuclear Regulatory Commission, Nureg/ia-108.

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