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Research Papers

Experimental Demonstration of AHWR Safety During Prolonged Station Black Out

[+] Author and Article Information
Mukesh Kumar

Reactor Engineering Division,
Reactor Design and Development Group,
Bhabha Atomic Research Centre,
Trombay,
Mumbai 400 085, India
e-mail: mukeshd@barc.gov.in

P. K. Verma, A. K. Nayak, A. Rama Rao

Reactor Engineering Division,
Reactor Design and Development Group,
Bhabha Atomic Research Centre,
Trombay,
Mumbai 400 085, India

1Corresponding author.

Manuscript received February 1, 2017; final manuscript received June 2, 2017; published online July 31, 2017. Assoc. Editor: Thambiayah Nitheanandan.

ASME J of Nuclear Rad Sci 3(4), 041012 (Jul 31, 2017) (8 pages) Paper No: NERS-17-1007; doi: 10.1115/1.4037031 History: Received February 01, 2017; Revised June 02, 2017

Fukushima accident has raised a strong concern and apprehension about the safety of a nuclear reactor failing to remove the decay heat following an extreme event. After Fukushima accident, the reactor designers worldwide analyzed the safety margin of the existing and new generation nuclear power plants for such an event. Advanced heavy water reactor (AHWR), designed in India, was also analyzed for even more severe conditions than occurred at Fukushima. AHWR equipped with several passive systems showed its robustness against this type of scenarios. However, several new passive systems were incorporated in AHWR design for maintaining the integrity of the reactor at least for 7 days as a grace period. A passive moderator cooling system (PMCS) and a passive endshield cooling system (PECS) were among the newly introduced safety system in AHWR. An experimental test facility simulating the prolonged station blackout (SBO) case in AHWR has been designed and built. Experiments have been performed in the test facility for simulated conditions of prolonged SBO. The current study shows the performance of AHWR during prolonged SBO case through simulation in the integral test facility. The results indicate that AHWR design is capable of removing decay heat for prolonged period without operator interference.

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Figures

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Fig. 1

Schematic of advanced heavy water reactor

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Fig. 2

Schematic of ICS and GDWP along with MHTS of AHWR

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Fig. 3

Schematic of passive moderator and passive endshield cooling system

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Fig. 4

Components of passive moderator and passive endshield cooling system: (1)—calandria vessel, (2)—heat exchanger, (3)—hot leg, (4)—gravity driven water pool (GDWP), (5)—primary natural circulation loop, (6)—secondary natural circulation loop, (7)—endshield vessel, and (8)—endshield cooling natural circulation loop

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Fig. 5

Schematic of integral test facility for simulating Fukushima type scenario

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Fig. 6

Fluid temperature variation at calandria inlet/outlet and GDWP inlet/outlet

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Fig. 7

Fluid temperature variation at endshield vessel inlet and outlet

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Fig. 8

Temperature distribution inside calandria vessel: (a) at 1800 s, (b) at 3600 s, (c) at 10 h, and (d) at 7 days

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Fig. 9

Temperature distribution inside endshield vessel: (a) at 1800 s, (b) at 3600 s, (c) at 10 h, and (d) at 7 days

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