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Research Papers

Thermal Hydraulic Safety Assessment of LLCB Test Blanket System in ITER Using Modified relap/scdapsim/mod4.0 Code

[+] Author and Article Information
S. P. Saraswat

Nuclear Engineering and
Technology Programme,
Indian Institute of Technology Kanpur,
Kanpur 208016, India
e-mails: satyasar@iitk.ac.in; satyasivam@gmail.com

P. Munsh

Nuclear Engineering and
Technology Programme,
Indian Institute of Technology Kanpur,
Kanpur 208016, India
e-mail: pmunshi@iitk.ac.in

A. Khanna

Nuclear Engineering and
Technology Programme,
Indian Institute of Technology Kanpur,
Kanpur 208016, India
e-mail: akhanna@iitk.ac.in

C. Allison

Innovative Systems Software,
Idaho Falls, ID 83406
e-mail: iss@cableone.net

Manuscript received October 9, 2016; final manuscript received December 8, 2017; published online March 5, 2018. Editor: Igor Pioro.

ASME J of Nuclear Rad Sci 4(2), 021001 (Mar 05, 2018) (10 pages) Paper No: NERS-16-1138; doi: 10.1115/1.4038823 History: Received October 09, 2016; Revised December 08, 2017

This work attempts to investigate the thermal hydraulic safety of lithium lead ceramic breeder (LLCB) test blanket system (TBS) in International Thermonuclear Experimental Reactor (ITER) with the help of modified thermal hydraulic code relap/scdapsim/mod4.0. The design basis accidents, in-vessel and ex-vessel loss of coolant of first wall (FW) of test blanket module (TBM) are analyzed for this safety assessment. The sequence of accidents analyzed was started with postulated initiating events (PIEs). A detailed modeling of first wall helium cooling system (FWHCS) loop and lithium lead cooling system (LLCS) is presented. The analysis of steady-state normal operation along with 10 s power excursion before the accident is also discussed in order to better understanding of initial condition of accidents. The analysis discusses a number of safety concerns and issues that may result from the TBM component failure, such as vacuum vessel (VV) pressurization, TBM FW temperature profile, passive decay heat removal capability of TBM structure, pressurization of port cell and Tokomak cooling water system vault annex (TCWS-VA) and to check the capability of passive safety system (vacuum vessel pressure suppression system (VVPSS)). The analysis shows that in these accident scenarios, the critical parameters have reasonable safety margins.

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References

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Figures

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Fig. 1

Thermal hydraulic nodalization of TBM FWHCS

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Fig. 2

relap5 modeling of TBM FW and double ended break of four TBM FW channels in case of in-vessel LOCA

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Fig. 3

Thermal hydraulic nodalization of TBM LLCS

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Fig. 4

Thermal hydraulic nodalization diagram VVPSS

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Fig. 5

Steady-state coolant temperature at various locations of LLCS loop

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Fig. 6

Steady-state coolant temperature at various locations of TBM FWHCS

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Fig. 7

Steady-state TBM FW temperature

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Fig. 8

Steady-state helium coolant pressure at various locations of TBM FWHCS

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Fig. 9

Steady-state mass flow rate at various locations of TBM FWHCS

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Fig. 10

Test blanket module FW temperature evolution during accident in-vessel LOCA

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Fig. 11

Pressure profile of TBM FW and VV during in-vessel LOCA

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Fig. 12

Vacuum vessel and VVPSS tank pressure during in-vessel LOCA

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Fig. 13

Test blanket module FW temperature during ex-vessel LOCA

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Fig. 14

Pressure profile of TBM FW and VV during ex-vessel LOCA

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Fig. 15

Pressurization of port cell, TCWS-VA, VV and VVPSS ST pool during ex-vessel LOCA

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Fig. 16

Pressurization TCWS-VA during ex-vessel LOCA

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Fig. 17

Steam masses in TCWS building, port cell and gallery during ex-vessel LOCA

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