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Research Papers

Ex-Vessel Loss of Coolant Accident Analysis of ITER Divertor Cooling System Using Modified RELAP/SCADAPSIM/Mod 4.0

[+] 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. Munshi

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 March 27, 2017; final manuscript received June 14, 2017; published online July 31, 2017. Assoc. Editor: Xu Cheng.

ASME J of Nuclear Rad Sci 3(4), 041009 (Jul 31, 2017) (13 pages) Paper No: NERS-17-1021; doi: 10.1115/1.4037188 History: Received March 27, 2017; Revised June 14, 2017

The initial design of ITER incorporated the use of carbon fiber composites in high heat flux regions and tungsten was used for low heat flux regions. The current design includes tungsten for both these regions. The present work includes thermal hydraulic modeling and analysis of ex-vessel loss of coolant accident (LOCA) for the divertor (DIV) cooling system. The purpose of this study is to show that the new concept of full tungsten divertor is able to withstand in the accident scenarios. The code used in this study is RELAP/SCADAPSIM/MOD 4.0. A parametric study is also carried out with different in-vessel break sizes and ex-vessel break locations. The analysis discusses a number of safety concerns that may result from the accident scenarios. These concerns include vacuum vessel (VV) pressurization, divertor temperature profile, passive decay heat removal capability of structure, and pressurization of tokamak cooling water system. The results show that the pressures and temperatures are kept below design limits prescribed by ITER organization.

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References

Figures

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Fig. 1

Schematic of ITER DV-PHTS loop

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Fig. 2

Thermal hydraulic nodalization of ITER divertor cooling system

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Fig. 3

RELAP/SCADAPSIM nodalization diagram VVPSS

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Fig. 4

Divertor cassette heat structures

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Fig. 5

(a) Steady-state lower IVT tungsten surface temperature, (b) steady-state divertor inlet outlet temperature, (c) steady-state DV-PHTS loop main pump mass flow rate, and (d) steady-state divertor inlet and outlet pressure

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Fig. 6

(a) Divertor lower IVT tungsten surface temperature profile during ex-vessel LOCA, (b) pressure profile of VV and TCWS during ex-vessel LOCA, (c) ex-vessel break mass flow rate, and (d) in-vessel break mass flow rate

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Fig. 7

Ex-vessel break mass flow rate

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Fig. 8

In-vessel break mass flow rate

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Fig. 9

Divertor lower IVT tungsten surface temperature profile during ex-vessel LOCA

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Fig. 10

Pressure profile of VV during ex-vessel LOCA

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Fig. 11

Pressure profile of TCWS vault during ex-vessel LOCA

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Fig. 12

VVPSS bleed line and rupture disk mass flow rates

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Fig. 13

Drain tank line mass flow rates

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Fig. 14

Pressure profile of VV with different in-vessel break sizes during ex-vessel LOCA

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Fig. 15

Pressure profile of TCWS vault with different in-vessel break sizes during ex-vessel LOCA

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Fig. 16

Temperature profile of lower DV-IVT tungsten surface with different in-vessel break sizes during ex-vessel LOCA

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Fig. 17

Pressurization trend of TCWS vault at different locations of ex-vessel break

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Fig. 18

Ex-vessel mass flow rate with different control volume size cases: (a) smaller volume case and (b) larger volume

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