Static and dynamic sensitivity analysis of corrosion product activity in primary coolant circuits of pressurized water reactors-Reference-Cited by-同舟云学术

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Static and dynamic sensitivity analysis of corrosion product activity in primary coolant circuits of pressurized water reactors

Published:2010-09 Issue:7 Volume:52 Page:648-654
ISSN:0149-1970
Container-title:Progress in Nuclear Energy
language:en
Short-container-title:Progress in Nuclear Energy

Author:

Mirza Sikander M.,Rafique M.,Ahmad Farooq,Mirza Nasir M.

Publisher

Elsevier BV

Subject

Waste Management and Disposal,Energy Engineering and Power Technology,Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference32 articles.

1. Uncertainty quantification, sensitivity analysis, and data assimilation for nuclear systems simulation;Abdel-Khalik;Nucl. Data Sheets,2008

2. Sensitivity analysis of thermohydraulic systems via generalized perturbation theory (HGPT) methods;Andrade Lima;Ann. Nucl. Energy,1993

3. Mass transfer in turbulent pipe flow measured by electrochemical method;Berger;Int. J. Heat Mass Transfer,1977

4. Uncertainty and sensitivity analyses of the Kozloduy pump trip test using coupled thermal-hydraulic 3D kinetics code;Bousbia Salah;Nucl. Eng. Des.,2006

5. Mechanism of detachment of colloidal particles from a flat substrate in turbulent flow;Cleaver;J. Coll. Interf. Sci.,1973

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1. An adjoint sensitivity analysis of the Telegrapher’s neutron kinetic equations;Annals of Nuclear Energy;2022-03

2. Evaluation of activated corrosion products in primary coolant circuit of AP-1000 under grid frequency stability mode;Annals of Nuclear Energy;2019-03

3. Dynamic response analysis of corrosion products activity under steady state operation and Mechanical Shim based power-maneuvering transients in AP-1000;Annals of Nuclear Energy;2018-05

4. The development of two-phase three-node model used to simulate the transport of ACPs;Progress in Nuclear Energy;2017-05

5. Parametric Study of Time-Dependent Corrosion Product Activity due to56Mn,58Co, and60Co in the Primary Coolant Circuit of a Typical Pressurized Water Reactor;Journal of Chemistry;2015

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