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Statements

Subject Item
n2:RIV%2F68407700%3A21340%2F14%3A00220101%21RIV15-MSM-21340___
rdf:type
n11:Vysledek skos:Concept
rdfs:seeAlso
http://dx.doi.org/10.1016/j.radphyschem.2014.05.038
dcterms:description
Thorium fuel is considered as a viable alternative to the uranium fuel used in the current generation of nuclear power plants. Switch from uranium to thorium means a complete change of composition of the spent nuclear fuel produced as a result of the fuel depletion during operation of a reactor. If the Th-U fuel cycle is implemented, production of minor actinides in the spent fuel is negligible. This is favourable for the spent fuel disposal. On the other hand, thorium fuel utilisation is connected with production of 232U, which decays via several alpha decays into a strong gamma emitter 208Tl. Presence of this nuclide might complicate manipulations with the irradiated thorium fuel. Monte-Carlo computation code MCNPX can be used to simulate thorium fuel depletion in a VVER-1000 reactor. The calculated actinide composition will be analysed and dose rate from produced gamma radiation will be calculated. The results will be compared to the reference uranium fuel. Dependence of the dose rate on time of decay after the end of irradiation in the reactor will be analysed. This study will compare the radiological hazard of the spent thorium and uranium fuel handling. Thorium fuel is considered as a viable alternative to the uranium fuel used in the current generation of nuclear power plants. Switch from uranium to thorium means a complete change of composition of the spent nuclear fuel produced as a result of the fuel depletion during operation of a reactor. If the Th-U fuel cycle is implemented, production of minor actinides in the spent fuel is negligible. This is favourable for the spent fuel disposal. On the other hand, thorium fuel utilisation is connected with production of 232U, which decays via several alpha decays into a strong gamma emitter 208Tl. Presence of this nuclide might complicate manipulations with the irradiated thorium fuel. Monte-Carlo computation code MCNPX can be used to simulate thorium fuel depletion in a VVER-1000 reactor. The calculated actinide composition will be analysed and dose rate from produced gamma radiation will be calculated. The results will be compared to the reference uranium fuel. Dependence of the dose rate on time of decay after the end of irradiation in the reactor will be analysed. This study will compare the radiological hazard of the spent thorium and uranium fuel handling.
dcterms:title
Comparison of the radiological hazard of thorium and uranium spent fuels from VVER-1000 reactor Comparison of the radiological hazard of thorium and uranium spent fuels from VVER-1000 reactor
skos:prefLabel
Comparison of the radiological hazard of thorium and uranium spent fuels from VVER-1000 reactor Comparison of the radiological hazard of thorium and uranium spent fuels from VVER-1000 reactor
skos:notation
RIV/68407700:21340/14:00220101!RIV15-MSM-21340___
n4:aktivita
n7:S n7:I
n4:aktivity
I, S
n4:cisloPeriodika
November
n4:dodaniDat
n14:2015
n4:domaciTvurceVysledku
n15:5204240
n4:druhVysledku
n8:J
n4:duvernostUdaju
n19:S
n4:entitaPredkladatele
n6:predkladatel
n4:idSjednocenehoVysledku
8243
n4:idVysledku
RIV/68407700:21340/14:00220101
n4:jazykVysledku
n10:eng
n4:klicovaSlova
MCNPX; Radiological hazard; Spent thorium fuel; Spent uranium fuel
n4:klicoveSlovo
n13:Spent%20thorium%20fuel n13:MCNPX n13:Spent%20uranium%20fuel n13:Radiological%20hazard
n4:kodStatuVydavatele
GB - Spojené království Velké Británie a Severního Irska
n4:kontrolniKodProRIV
[4EB123C0E720]
n4:nazevZdroje
Radiation Physics and Chemistry
n4:obor
n17:JF
n4:pocetDomacichTvurcuVysledku
1
n4:pocetTvurcuVysledku
1
n4:rokUplatneniVysledku
n14:2014
n4:svazekPeriodika
104
n4:tvurceVysledku
Frýbort, Jan
n4:wos
000341463600086
s:issn
0969-806X
s:numberOfPages
6
n18:doi
10.1016/j.radphyschem.2014.05.038
n16:organizacniJednotka
21340