Search Results - "TVERBERG, T"

Fission gas release behaviour of a 103 GWd/tHM fuel disc during a 1200 °C annealing test by NOIROT, J, PONTILLON, Y, YAGNIK, S, TURNBULL, J. A, TVERBERG, T

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Heterogeneous UO2 fuel irradiated up to a high burn-up: Investigation of the HBS and of fission product releases by Noirot, J., Lamontagne, J., Nakae, N., Kitagawa, T., Kosaka, Y., Tverberg, T.

“…A UO2 fuel with a heterogeneous distribution of 235U was irradiated up to a high burn-up in the Halden Boiling Water Reactor (HBWR). The last 100days of…”
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Under irradiation issues of the CSZ–based inert matrix fuels from IFA-652 Halden experiment by Calabrese, R., Vettraino, F., Tverberg, T.

“…The renewal of interest in Fast Reactors (FR) deployment as possible answer to the future perspective of natural uranium shortage has led to reconsider the…”
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Inert matrix and thoria fuel irradiation at an international research reactor by Streit, M., Tverberg, T., Wiesenack, W., Vettraino, F.

“…A major issue in the public debate on nuclear power, is how to break down the large plutonium stockpiles. Different concepts have been developed during the…”
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Yttrium stabilised zirconia inert matrix fuel irradiation at an international research reactor by Streit, M., Wiesenack, W., Tverberg, T., Hellwig, Ch, Oberländer, B.C.

“…Different concepts have been developed during the last decade to transmute transuranium elements (TRU) using uranium-free inert matrix fuels (IMF) in a…”
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Inert matrix fuel behaviour in test irradiations by Hellwig, Ch, Streit, M., Blair, P., Tverberg, T., Klaassen, F.C., Schram, R.P.C., Vettraino, F., Yamashita, T.

“…Among others, three large irradiation tests on inert matrix fuels have been performed during the last five years: the two irradiation tests IFA-651 and IFA-652…”
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Fission gas release behaviour of a 103GWd/tHM fuel disc during a 1200°C annealing test by Noirot, J., Pontillon, Y., Yagnik, S., Turnbull, J.A., Tverberg, T.

“…Within the Nuclear Fuel Industry Research (NFIR) program, several fuel variants, in the form of thin circular discs, were irradiated in the Halden Boiling…”
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Fission gas release behaviour of a 103 GWd/t sub(HM) fuel disc during a 1200 degree C annealing test by Noirot, J, Pontillon, Y, Yagnik, S, Turnbull, JA, Tverberg, T

“…Within the Nuclear Fuel Industry Research (NFIR) program, several fuel variants, in the form of thin circular discs, were irradiated in the Halden Boiling…”
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Fission gas release behaviour of a 103 GWd/t sub(HM) fuel disc during a 1200 [degrees]C annealing test by Noirot, J, Pontillon, Y, Yagnik, S, Turnbull, J A, Tverberg, T

“…Within the Nuclear Fuel Industry Research (NFIR) program, several fuel variants, in the form of thin circular discs, were irradiated in the Halden Boiling…”
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Irradiation testing of enhanced uranium oxide fuels by Insulander Björk, Klara, Kelly, Julian F., Vitanza, Carlo, Drera, Saleem S., Holcombe, Scott, Tverberg, Terje, Tuomisto, Harri, Wright, Jonathan, Sarsfield, Mark, Blench, Trevor, Yang, Jae Ho, Kim, Hyun-Gil, Kim, Dong-Joo, Lau, Cheuk W.

“…•Irradiation testing of uranium oxide fuel enhanced with Cr, SiO2/TiO2 and ThO2.•Irradiation testing of cladding coated with (Fe,Cr,Al) and (Cr,Al) alloys.•All…”
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Commercial thorium fuel manufacture and irradiation: Testing (Th, Pu) O 2 and (Th, U) O 2 in the “Seven-Thirty” program by Insulander Björk, Klara, Drera, Saleem S., Kelly, Julian F., Vitanza, Carlo, Helsengreen, Christian, Tverberg, Terje, Sobieska, Matylda, Oberländer, Barbara C., Tuomisto, Harri, Kekkonen, Laura, Wright, Jonathan, Bergmann, Uffe, Mathers, Daniel P.

“…Thorium based fuels are being tested in the Halden Research Reactor in Norway with the aim of producing the data necessary for licensing of these fuels in…”
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The OECD Halden reactor project fuels testing programme: methods, selected results and plans by Wiesenack, Wolfgang, Tverberg, Terje

“…The fuels testing programme conducted in the Halden reactor (heavy boiling water reactor (HBWR)) is aimed at providing data for a mechanistic understanding of…”
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Inert matrix and thoria fuel irradiation at an international research reactor : Nuclear Materials by STREIT, M, TVERBERG, T, WIESENACK, W, VETTRAINO, F

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Yttrium stabilised zirconia inert matrix fuel irradiation at an international research reactor : Nuclear Materials by STREIT, M, WIESENACK, W, TVERBERG, T, HELLWIG, Ch, OBERLÄNDER, B. C

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Inert matrix fuel behaviour in test irradiations : Nuclear Materials by HELLWIG, Ch, STREIT, M, BLAIR, P, TVERBERG, T, KLAASSEN, F. C, SCHRAM, R. P. C, VETTRAINO, F, YAMASHITA, T

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