Research Papers

Thermal Analysis of Irradiated Fuel Subassemblies and Fuel Pins During Storage in Concrete Pits of Head-End Facility

[+] Author and Article Information
M. Rajendrakumar

Indira Gandhi Centre for Atomic Research,
Kalpakkam 603102, Tamilnadu, India
e-mail: mrk@igcar.gov.in

K. Velusamy

Indira Gandhi Centre for Atomic Research,
Kalpakkam 603102, Tamilnadu, India
e-mail: kvelu@igcar.gov.in

P. Selvaraj

Indira Gandhi Centre for Atomic Research,
Kalpakkam 603102, Tamilnadu, India
e-mail: pselva@igcar.gov.in

P. Chellapandi

Indira Gandhi Centre for Atomic Research,
Kalpakkam 603102, Tamilnadu, India
e-mail: pcp@igcar.gov.in

Contributed by the Heat Transfer Division of ASME for publication in the JOURNAL OF THERMAL SCIENCE AND ENGINEERING APPLICATIONS. Manuscript received May 13, 2014; final manuscript received March 2, 2015; published online November 11, 2015. Assoc. Editor: Sumanta Acharya.

J. Thermal Sci. Eng. Appl 8(1), 011016 (Nov 11, 2015) (9 pages) Paper No: TSEA-14-1120; doi: 10.1115/1.4030733 History: Received May 13, 2014

Irradiated fuel subassembly (SA)/fuel pins, with significant decay heat are transported from reactor and stored in hot cells (HCs) before reprocessing. During transportation they are heavily shielded and no forced cooling is provided. The HCs are made of concrete structures, the outer surfaces of which are force cooled. During these processes, the fuel pin clad temperature and concrete temperatures are to be limited within specific safety limits. These temperatures are function of the decay power and geometric details of surrounding structures. To predict these temperatures, three-dimensional conjugate conduction–convection–radiation heat transfer analysis has been carried out. For this purpose, the computational fluid dynamics (CFD) code STAR-CD has been utilized, wherein individual fuel pins, steel cans, hexagonal wrapper, lead shielding blocks, and concrete structures have been considered in detail. Based on parametric studies pertaining to fuel pin transportation, it is established that for a decay power of 150 W, natural convection is adequate with maximum clad temperature of 686 K. From the studies related to storage in HCs, it is seen that nine fast breeder test reactor (FBTR) SA can stored in hot cell-1 (HC-1), with a decay power of 31.3 W per SA, to respect the temperature limits. For 3 prototype fast breeder reactor (PFBR) cans and 2 FBTR cans stored in hot cell-3 (HC-3), a decay power of 12.5 W per FBTR can and 44 W per PFBR can, can be handled without exceeding temperature limits.

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Fig. 1

Flowchart of SA/fuel pin movement during (a) transportation and (b) storage

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Fig. 2

Transportation cask along with storage pot and SSA

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Fig. 3

SA platform for HC-1 cell

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Fig. 4

SA platform for HC-3 cell

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Fig. 5

Computational mesh (a) and expanded view of computational mesh near fuel pins (b) of transportation cask

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Fig. 6

Computational mesh of FBTR fuel SA platform for HC-1

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Fig. 7

Velocity vectors of fluid (m/s) inside transportation cask (decay power = 150 W/SA)

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Fig. 8

Temperature contours (K) of storage pot with storage subassembly and fuel pins (decay power = 150 W per SA)

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Fig. 9

Temperature contours (K) of storage pot along with SSA and fuel pins at midplane of bottom set of fuel pins (decay power = 150 W per SA)

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Fig. 10

Temperature contours (K) of HC-1 concrete vault at midsection of active region for a decay power of 174 W per SA (zoomed view shows temperatures in fuel pin and clad)

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Fig. 11

Temperature contours (K) of outer surface of concrete vault of HC-1 (decay power = 174 W per SA and number of SA = 9)

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Fig. 12

Temperature contours (K) of outer surface of vault of HC-3 with both PFBR and FBTR pins (decay power=174 W for 61 FBTR pins, 629 W for 91 PFBR pins)




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