Research Papers

A Space–Time-Dependent Study of Control Rods Withdrawal in a Large-Size Pressurized Water Reactor

[+] Author and Article Information
Sanjeev Kumar

Department of Mechanical Engineering,
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
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,
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 3(1), 011015 (Dec 20, 2016) (8 pages) Paper No: NERS-16-1007; doi: 10.1115/1.4034478 History: Received January 25, 2016; Accepted August 06, 2016

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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Grahic Jump Location
Fig. 1

CA banks’ distribution in the core

Grahic Jump Location
Fig. 2

Variation of (a) total power and (b) total reactivity with time in different cases

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Fig. 3

Contour plots of relative radial power distribution at the 3rd axial node (≈19.2  cm from core bottom) in different cases at SCRAM level (110% of FP)

Grahic Jump Location
Fig. 4

Surface plots of relative radial power distribution at the 3rd axial node (≈19.2  cm from core bottom) in different cases at SCRAM level (110% of FP)

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Fig. 5

Axial heat flux profiles at peak positions

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Fig. 6

Radial temperature profiles at peak central line temperature locations



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