Investigating the ESBWR stability with experimental and numerical tools: A comparative study. Rohde, M., Marcel, C., P., Manera, A., Van der Hagen, T., H., J., J., & Shiralkar, B. Nuclear Engineering and Design, 240(2):375-384, 2010.
abstract   bibtex   
In this work, the stability of the Economic Simplified Boiling Water Reactor (ESBWR) has been studied by using a Freon-134a based experimental facility (GENESIS) and two system codes, being ATHLET 2.0a and (to a lesser extent) TRACG. During setting up the GENESIS facility and the numerical calculations, a great effort has been made to approximate the ESBWR system as accurate as possible. In general, it was found that a sufficient margin to instability exists regarding the ESBWRs nominal point. In addition, a comparison was made between the numerical and experimental results for both the thermal-hydraulic system and the reactor system. Deviations were found between the numerical and experimental results, in spite of the close similarity between the GENESIS facility and the definition of the ESBWR system in the system code. This result shows that predictions regarding real nuclear reactors, based on modeled systems, should be taken with care. ?? 2008 Elsevier B.V. All rights reserved.
@article{
 title = {Investigating the ESBWR stability with experimental and numerical tools: A comparative study},
 type = {article},
 year = {2010},
 identifiers = {[object Object]},
 keywords = {boiling water-reactors natural circulation bwrs vo},
 pages = {375-384},
 volume = {240},
 city = {Delft Univ Technol, Sect Phys Nucl Reactors, NL-2629 JB Delft, Netherlands Forschungszentrum Dresden Rossendorf, D-01314 Dresden, Germany Paul Scherrer Inst, Villigen, Switzerland GE Energy Nucl, San Jose, CA USA},
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 notes = {Sp. Iss. SI<br/>556qv<br/>Times Cited:11<br/>Cited References Count:23},
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 abstract = {In this work, the stability of the Economic Simplified Boiling Water Reactor (ESBWR) has been studied by using a Freon-134a based experimental facility (GENESIS) and two system codes, being ATHLET 2.0a and (to a lesser extent) TRACG. During setting up the GENESIS facility and the numerical calculations, a great effort has been made to approximate the ESBWR system as accurate as possible. In general, it was found that a sufficient margin to instability exists regarding the ESBWRs nominal point. In addition, a comparison was made between the numerical and experimental results for both the thermal-hydraulic system and the reactor system. Deviations were found between the numerical and experimental results, in spite of the close similarity between the GENESIS facility and the definition of the ESBWR system in the system code. This result shows that predictions regarding real nuclear reactors, based on modeled systems, should be taken with care. ?? 2008 Elsevier B.V. All rights reserved.},
 bibtype = {article},
 author = {Rohde, M. and Marcel, C. P. and Manera, A. and Van der Hagen, T. H J J and Shiralkar, B.},
 journal = {Nuclear Engineering and Design},
 number = {2}
}

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