Determination of plutonium and uranium content and burnup using six group delayed neutrons

T. Akyurek; S. Usman

doi:10.1016/j.net.2019.01.005

Determination of plutonium and uranium content and burnup using six group delayed neutrons

T. Akyurek^*, S. Usman

^*Bu çalışma için yazışmadan sorumlu yazar

Araştırma sonucu: Dergiye katkı › Makale › bilirkişi

3 Atıf (Scopus)

Özet

In this study, investigation of spent fuel was performed using six group delayed neutron parameters. Three used fuels (F1, F2, and F11) which are burnt over the years in the core of Missouri University of Science and Technology Reactor (MSTR), were investigated. F16 fresh fuel was used as plutonium free fuel element and compared with irradiated used fuels to develop burnup and Pu discrimination method. The fast fission factor of the MSTR was calculated to be 1.071 which was used for burnup calculations. Burnup values of F2 and F11 fuel elements were estimated to be 1.98 g and 2.7 g, respectively. ²³⁹Pu conversion was calculated to be 0.36 g and 0.50 g for F2 and F11 elements, respectively.

Orijinal dil	İngilizce
Sayfa (başlangıç-bitiş)	943-948
Sayfa sayısı	6
Dergi	Nuclear Engineering and Technology
Hacim	51
Basın numarası	4
DOI'lar	https://doi.org/10.1016/j.net.2019.01.005
Yayın durumu	Yayınlandı - Tem 2019
Harici olarak yayınlandı	Evet

Bibliyografik not

Publisher Copyright:
© 2019

Finansman

Authors would like to express their sincere appreciation for reactor staff for providing support during data collection. This study was supported by Marmara University, Scientific Research Commission (BAPKO) under the research project FEN-A-131016-0466 .

Finansörler	Finansör numarası
Marmara Üniversitesi	FEN-A-131016-0466

Belgeye Erişim

10.1016/j.net.2019.01.005

Diğer Dosyalar ve Linkler

Link to publication in Scopus

Alıntı Yap

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title = "Determination of plutonium and uranium content and burnup using six group delayed neutrons",

abstract = "In this study, investigation of spent fuel was performed using six group delayed neutron parameters. Three used fuels (F1, F2, and F11) which are burnt over the years in the core of Missouri University of Science and Technology Reactor (MSTR), were investigated. F16 fresh fuel was used as plutonium free fuel element and compared with irradiated used fuels to develop burnup and Pu discrimination method. The fast fission factor of the MSTR was calculated to be 1.071 which was used for burnup calculations. Burnup values of F2 and F11 fuel elements were estimated to be 1.98 g and 2.7 g, respectively. 239Pu conversion was calculated to be 0.36 g and 0.50 g for F2 and F11 elements, respectively.",

keywords = "Burnup, Delay neutrons, Fuel elements, Six group parameters",

author = "T. Akyurek and S. Usman",

note = "Publisher Copyright: {\textcopyright} 2019",

year = "2019",

month = jul,

doi = "10.1016/j.net.2019.01.005",

language = "English",

volume = "51",

pages = "943--948",

journal = "Nuclear Engineering and Technology",

issn = "1738-5733",

publisher = "Korean Nuclear Society",

number = "4",

}

TY - JOUR

T1 - Determination of plutonium and uranium content and burnup using six group delayed neutrons

AU - Akyurek, T.

AU - Usman, S.

PY - 2019/7

Y1 - 2019/7

N2 - In this study, investigation of spent fuel was performed using six group delayed neutron parameters. Three used fuels (F1, F2, and F11) which are burnt over the years in the core of Missouri University of Science and Technology Reactor (MSTR), were investigated. F16 fresh fuel was used as plutonium free fuel element and compared with irradiated used fuels to develop burnup and Pu discrimination method. The fast fission factor of the MSTR was calculated to be 1.071 which was used for burnup calculations. Burnup values of F2 and F11 fuel elements were estimated to be 1.98 g and 2.7 g, respectively. 239Pu conversion was calculated to be 0.36 g and 0.50 g for F2 and F11 elements, respectively.

AB - In this study, investigation of spent fuel was performed using six group delayed neutron parameters. Three used fuels (F1, F2, and F11) which are burnt over the years in the core of Missouri University of Science and Technology Reactor (MSTR), were investigated. F16 fresh fuel was used as plutonium free fuel element and compared with irradiated used fuels to develop burnup and Pu discrimination method. The fast fission factor of the MSTR was calculated to be 1.071 which was used for burnup calculations. Burnup values of F2 and F11 fuel elements were estimated to be 1.98 g and 2.7 g, respectively. 239Pu conversion was calculated to be 0.36 g and 0.50 g for F2 and F11 elements, respectively.

KW - Burnup

KW - Delay neutrons

KW - Fuel elements

KW - Six group parameters

UR - http://www.scopus.com/inward/record.url?scp=85066113168&partnerID=8YFLogxK

U2 - 10.1016/j.net.2019.01.005

DO - 10.1016/j.net.2019.01.005

M3 - Article

AN - SCOPUS:85066113168

SN - 1738-5733

VL - 51

SP - 943

EP - 948

JO - Nuclear Engineering and Technology

JF - Nuclear Engineering and Technology

IS - 4

ER -

Determination of plutonium and uranium content and burnup using six group delayed neutrons

Özet

Bibliyografik not

Finansman

Belgeye Erişim

Diğer Dosyalar ve Linkler

Parmak izi

Alıntı Yap