OSU tritium control and mitigation strategy for FHRs

In Hun Kim; Xiao Wu; David Arcilesi; Xiaodong Sun; R. Christensen; Piyush Sabharwall

OSU tritium control and mitigation strategy for FHRs

In Hun Kim
, Xiao Wu
, David Arcilesi
, Xiaodong Sun
, R. Christensen
, Piyush Sabharwall

Nuclear Reactor Technology

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

Abstract

Neutron activation of FLiBe in a FHR generates a lot of tritium, a radio-isotope of hydrogen, whose uptake may induce cancer. Main forms of tritium in the FHR are corrosive TF and permeable HT. To solve the tritium issue and economic benefit in the FHR, a two loop FHR system with tritium removal facility no.1 and no.2, and coated heat exchangers are suggested, based on a tritium recovery technology in the fusion field.

Original language	English
Title of host publication	10th international topical meeting on nuclear thermal hydraulics, operation and safety (NUTHOS-10)
State	Published - Jul 1 2014
Event	The 10th International Topical Meeting on Nuclear Thermal Hydraulics, Operation and Safety (NUTHOS-10) - Okinawa, Japan Duration: Dec 14 2014 → Dec 18 2014

Conference

Conference	The 10th International Topical Meeting on Nuclear Thermal Hydraulics, Operation and Safety (NUTHOS-10)
Country/Territory	Japan
City	Okinawa
Period	12/14/14 → 12/18/14

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Cite this

@inproceedings{13e43399a27e4e1192900d4b91192140,

title = "OSU tritium control and mitigation strategy for FHRs",

abstract = "Neutron activation of FLiBe in a FHR generates a lot of tritium, a radio-isotope of hydrogen, whose uptake may induce cancer. Main forms of tritium in the FHR are corrosive TF and permeable HT. To solve the tritium issue and economic benefit in the FHR, a two loop FHR system with tritium removal facility no.1 and no.2, and coated heat exchangers are suggested, based on a tritium recovery technology in the fusion field.",

author = "Kim, \{In Hun\} and Xiao Wu and David Arcilesi and Xiaodong Sun and R. Christensen and Piyush Sabharwall",

year = "2014",

month = jul,

day = "1",

language = "English",

booktitle = "10th international topical meeting on nuclear thermal hydraulics, operation and safety (NUTHOS-10)",

note = "The 10th International Topical Meeting on Nuclear Thermal Hydraulics, Operation and Safety (NUTHOS-10) ; Conference date: 14-12-2014 Through 18-12-2014",

}

Kim, IH, Wu, X, Arcilesi, D, Sun, X, Christensen, R & Sabharwall, P 2014, OSU tritium control and mitigation strategy for FHRs. in 10th international topical meeting on nuclear thermal hydraulics, operation and safety (NUTHOS-10). The 10th International Topical Meeting on Nuclear Thermal Hydraulics, Operation and Safety (NUTHOS-10), Okinawa, Japan, 12/14/14. <https://inis.iaea.org/search/search.aspx?orig_q=RN:47072668>

TY - GEN

T1 - OSU tritium control and mitigation strategy for FHRs

AU - Kim, In Hun

AU - Wu, Xiao

AU - Arcilesi, David

AU - Sun, Xiaodong

AU - Christensen, R.

AU - Sabharwall, Piyush

PY - 2014/7/1

Y1 - 2014/7/1

N2 - Neutron activation of FLiBe in a FHR generates a lot of tritium, a radio-isotope of hydrogen, whose uptake may induce cancer. Main forms of tritium in the FHR are corrosive TF and permeable HT. To solve the tritium issue and economic benefit in the FHR, a two loop FHR system with tritium removal facility no.1 and no.2, and coated heat exchangers are suggested, based on a tritium recovery technology in the fusion field.

AB - Neutron activation of FLiBe in a FHR generates a lot of tritium, a radio-isotope of hydrogen, whose uptake may induce cancer. Main forms of tritium in the FHR are corrosive TF and permeable HT. To solve the tritium issue and economic benefit in the FHR, a two loop FHR system with tritium removal facility no.1 and no.2, and coated heat exchangers are suggested, based on a tritium recovery technology in the fusion field.

M3 - Conference contribution

BT - 10th international topical meeting on nuclear thermal hydraulics, operation and safety (NUTHOS-10)

T2 - The 10th International Topical Meeting on Nuclear Thermal Hydraulics, Operation and Safety (NUTHOS-10)

Y2 - 14 December 2014 through 18 December 2014

ER -

OSU tritium control and mitigation strategy for FHRs

Abstract

Conference

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