R&D program for the fuel qualification of research fast reactor MYRRHA

Research output: Contribution to report/book/conference proceedingsIn-proceedings paper

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R&D program for the fuel qualification of research fast reactor MYRRHA. / Delville, Rémi; Lemehov, Sergei; Sobolev, Vitaly; Boer, Brian; De Bremaecker, Anne; van der Merwe, Hanno; Verwerft, Marc.

Design, manufacturing and irradiation behaviour of fast reactor fuel. Vienna, Austria, 2013. p. 63-73.

Research output: Contribution to report/book/conference proceedingsIn-proceedings paper

Harvard

Delville, R, Lemehov, S, Sobolev, V, Boer, B, De Bremaecker, A, van der Merwe, H & Verwerft, M 2013, R&D program for the fuel qualification of research fast reactor MYRRHA. in Design, manufacturing and irradiation behaviour of fast reactor fuel. Vienna, Austria, pp. 63-73, 2011 - IAEA Technical Meeting on Design , Obninsk, Russian Federation, 2011-05-30.

APA

Vancouver

Delville R, Lemehov S, Sobolev V, Boer B, De Bremaecker A, van der Merwe H et al. R&D program for the fuel qualification of research fast reactor MYRRHA. In Design, manufacturing and irradiation behaviour of fast reactor fuel. Vienna, Austria. 2013. p. 63-73

Bibtex - Download

@inproceedings{72d140f29f4248508b5124475ea93976,
title = "R&D program for the fuel qualification of research fast reactor MYRRHA",
abstract = "The innovative fast spectrum experimental facility MYRRHA is being developed at the Belgian Nuclear Research Center SCK-CEN. MYRRHA, a flexible fast spectrum research reactor (50-100 MWth), is conceived as an accelerator driven system (ADS) demonstrator, able to operate in sub-critical and critical modes. It contains a proton accelerator of 600 MeV, a spallation target and a multiplying core with MOX fuel, cooled by liquid lead-bismuth. The project started in 1997 and the reactor is forecasted to be fully operational around 2022-2023. The driver fuel for the MYRRHA core is one of its key components. Plutonium-uranium dioxides mixture (MOX) with 30-35 {\%} of the reactor grade plutonium in heavy metal is the preferred choice. MOX fuel elements with stainless steel cladding have already been produced, qualified and used for the sodium cooled fast neutron reactors (SFR). However, the difference in the lead-bismuth coolant temperature and its interactions with the fuel elements with respect to the operating conditions of a SFR and the specific operating conditions caused by beam trip effects in ADS require substantial efforts for the fuel qualification. Of special concern is the corrosion behavior of the cladding materials in a lead-bismuth environment with the power profile envisaged for MYRRHA.",
keywords = "MYRRHA, fuel, corrosion, qualification, cladding",
author = "R{\'e}mi Delville and Sergei Lemehov and Vitaly Sobolev and Brian Boer and {De Bremaecker}, Anne and {van der Merwe}, Hanno and Marc Verwerft",
note = "Score = 3",
year = "2013",
month = "6",
language = "English",
isbn = "978-92-0-186510-6",
pages = "63--73",
booktitle = "Design, manufacturing and irradiation behaviour of fast reactor fuel",

}

RIS - Download

TY - GEN

T1 - R&D program for the fuel qualification of research fast reactor MYRRHA

AU - Delville, Rémi

AU - Lemehov, Sergei

AU - Sobolev, Vitaly

AU - Boer, Brian

AU - De Bremaecker, Anne

AU - van der Merwe, Hanno

AU - Verwerft, Marc

N1 - Score = 3

PY - 2013/6

Y1 - 2013/6

N2 - The innovative fast spectrum experimental facility MYRRHA is being developed at the Belgian Nuclear Research Center SCK-CEN. MYRRHA, a flexible fast spectrum research reactor (50-100 MWth), is conceived as an accelerator driven system (ADS) demonstrator, able to operate in sub-critical and critical modes. It contains a proton accelerator of 600 MeV, a spallation target and a multiplying core with MOX fuel, cooled by liquid lead-bismuth. The project started in 1997 and the reactor is forecasted to be fully operational around 2022-2023. The driver fuel for the MYRRHA core is one of its key components. Plutonium-uranium dioxides mixture (MOX) with 30-35 % of the reactor grade plutonium in heavy metal is the preferred choice. MOX fuel elements with stainless steel cladding have already been produced, qualified and used for the sodium cooled fast neutron reactors (SFR). However, the difference in the lead-bismuth coolant temperature and its interactions with the fuel elements with respect to the operating conditions of a SFR and the specific operating conditions caused by beam trip effects in ADS require substantial efforts for the fuel qualification. Of special concern is the corrosion behavior of the cladding materials in a lead-bismuth environment with the power profile envisaged for MYRRHA.

AB - The innovative fast spectrum experimental facility MYRRHA is being developed at the Belgian Nuclear Research Center SCK-CEN. MYRRHA, a flexible fast spectrum research reactor (50-100 MWth), is conceived as an accelerator driven system (ADS) demonstrator, able to operate in sub-critical and critical modes. It contains a proton accelerator of 600 MeV, a spallation target and a multiplying core with MOX fuel, cooled by liquid lead-bismuth. The project started in 1997 and the reactor is forecasted to be fully operational around 2022-2023. The driver fuel for the MYRRHA core is one of its key components. Plutonium-uranium dioxides mixture (MOX) with 30-35 % of the reactor grade plutonium in heavy metal is the preferred choice. MOX fuel elements with stainless steel cladding have already been produced, qualified and used for the sodium cooled fast neutron reactors (SFR). However, the difference in the lead-bismuth coolant temperature and its interactions with the fuel elements with respect to the operating conditions of a SFR and the specific operating conditions caused by beam trip effects in ADS require substantial efforts for the fuel qualification. Of special concern is the corrosion behavior of the cladding materials in a lead-bismuth environment with the power profile envisaged for MYRRHA.

KW - MYRRHA

KW - fuel

KW - corrosion

KW - qualification

KW - cladding

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/ezp_138941

UR - http://knowledgecentre.sckcen.be/so2/bibref/12445

M3 - In-proceedings paper

SN - 978-92-0-186510-6

SP - 63

EP - 73

BT - Design, manufacturing and irradiation behaviour of fast reactor fuel

CY - Vienna, Austria

ER -

ID: 213347