This work focuses on the safety analysis of a typical pressurized water reactor (PWR) for reactivity-initiated transients. These transients result from withdrawal of six sets of groups of control rods that may occur under control systems or other faults. NEA/OECD PWR benchmark is considered for the study. A 3D space–time kinetics code, “TRIKIN” (neutronic and thermal-hydraulics coupled code) is used to account for local changes in the neutron flux. These local changes in the neutron flux affect the total reactivity, local power, and temperature distribution. The safety parameters are the usual 3D radial power distribution, flux tilt, axial heat flux for the peak channel, and radial peak central line temperature profiles over the horizontal plane. These safety parameters studied in the incident progression up to reactor SCRAM level. The minimum departure from the nucleate boiling ratio (MDNBR) has been investigated quantitatively for all six cases. The case that gives maximum drop in MDNBR at SCRAM level is identified and its consequences are discussed. The study is of high importance in revealing the importance of grouping of control rods’ configurations, providing insight in developing strategy for designing the configuration and reactivity worth of groups of control rods and local/global reactor control systems for large-size PWRs.
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January 2017
Research Papers
A Space–Time-Dependent Study of Control Rods Withdrawal in a Large-Size Pressurized Water Reactor
Sanjeev Kumar,
Sanjeev Kumar
Department of Mechanical Engineering,
e-mail: sanjeevk@iitk.ac.in, sanjeev683@gmail.com
Indian Institute of Technology Kanpur
, Uttar Pradesh 208016
, India
e-mail: sanjeevk@iitk.ac.in, sanjeev683@gmail.com
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K. Obaidurrahman,
e-mail: obaid@aerb.gov.in
K. Obaidurrahman
Atomic Energy Regulatory Board
, Anushakti Nagar, Niyamak Bhavan, Mumbai 400094
, India
e-mail: obaid@aerb.gov.in
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Om Pal Singh,
Om Pal Singh
Visiting Professor
e-mail: singhompal@yahoo.com
Nuclear Engineering and Technology Programme, Indian Institute of Technology Kanpur
, Uttar Pradesh 208016
, India
e-mail: singhompal@yahoo.com
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Prabhat Munshi
Prabhat Munshi
Department of Mechanical Engineering,
e-mail: pmunshi@iitk.ac.in
Nuclear Engineering and Technology Programme, Indian Institute of Technology Kanpur
, Uttar Pradesh 208016
, India
e-mail: pmunshi@iitk.ac.in
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Sanjeev Kumar
Department of Mechanical Engineering,
e-mail: sanjeevk@iitk.ac.in, sanjeev683@gmail.com
Indian Institute of Technology Kanpur
, Uttar Pradesh 208016
, India
e-mail: sanjeevk@iitk.ac.in, sanjeev683@gmail.com
K. Obaidurrahman
Atomic Energy Regulatory Board
, Anushakti Nagar, Niyamak Bhavan, Mumbai 400094
, India
e-mail: obaid@aerb.gov.in
Om Pal Singh
Visiting Professor
e-mail: singhompal@yahoo.com
Nuclear Engineering and Technology Programme, Indian Institute of Technology Kanpur
, Uttar Pradesh 208016
, India
e-mail: singhompal@yahoo.com
Prabhat Munshi
Department of Mechanical Engineering,
e-mail: pmunshi@iitk.ac.in
Nuclear Engineering and Technology Programme, Indian Institute of Technology Kanpur
, Uttar Pradesh 208016
, India
e-mail: pmunshi@iitk.ac.in
Manuscript received January 25, 2016; final manuscript received August 6, 2016; published online December 20, 2016. Assoc. Editor: Masaki Morishita.
ASME J of Nuclear Rad Sci. Jan 2017, 3(1): 011015 (8 pages)
Published Online: December 20, 2016
Article history
Received:
January 25, 2016
Revision Received:
August 6, 2016
Accepted:
August 6, 2016
Citation
Kumar, S., Obaidurrahman, K., Singh, O. P., and Munshi, P. (December 20, 2016). "A Space–Time-Dependent Study of Control Rods Withdrawal in a Large-Size Pressurized Water Reactor." ASME. ASME J of Nuclear Rad Sci. January 2017; 3(1): 011015. https://doi.org/10.1115/1.4034478
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