Modeling Minor Actinide Bearing Blanket Fuels for Fast-Neutron Reactors

Research output: Report/bookER - External reportpeer-review

Standard

Modeling Minor Actinide Bearing Blanket Fuels for Fast-Neutron Reactors. / Lemehov, Sergei.

1 ed. SCK CEN, 2015. 106 p. (SCK•CEN Reports; No. ER-292).

Research output: Report/bookER - External reportpeer-review

Harvard

Lemehov, S 2015, Modeling Minor Actinide Bearing Blanket Fuels for Fast-Neutron Reactors. SCK•CEN Reports, no. ER-292, vol. 1, 1 edn, SCK CEN.

APA

Lemehov, S. (2015). Modeling Minor Actinide Bearing Blanket Fuels for Fast-Neutron Reactors. (1 ed.) (SCK•CEN Reports; No. ER-292). SCK CEN.

Vancouver

Lemehov S. Modeling Minor Actinide Bearing Blanket Fuels for Fast-Neutron Reactors. 1 ed. SCK CEN, 2015. 106 p. (SCK•CEN Reports; ER-292).

Author

Lemehov, Sergei. / Modeling Minor Actinide Bearing Blanket Fuels for Fast-Neutron Reactors. 1 ed. SCK CEN, 2015. 106 p. (SCK•CEN Reports; ER-292).

Bibtex - Download

@book{97625a5d207f4154b81a9e69bf904e12,
title = "Modeling Minor Actinide Bearing Blanket Fuels for Fast-Neutron Reactors",
abstract = "MABB fuels have been modeled with the MACROS code with specific interest to americium and neptunium transmutation, fuel swelling and effects of self-irradiation on thermal properties. SUPERFACT-1 rod SF6/SF14 consisting originally of (U,Am,Np)O2 pellets was recalculated. Fission gas release, burnup and transmutation behavior as calculated with the MACROS code are in good agreement with the reported PIE data. Disagreement between calculations and observations was revealed for restructuring and central void formation. PIE data show absence of columnar grains and central void, though there are some indications that under operation conditions fuel was close to onset. Due to low thermal conductivity calculated central temperature was higher than 1800°C providing conditions for the central void formation and restructuring. Further analysis of input data and models will be conducted. Also, code calculations were performed to simulate release of fission helium in conditions of MARIOS irradiation.",
keywords = "Americium, Neptunium, Phenix, MOX, Helium, SUPERFACT, MARINE, MARIOS",
author = "Sergei Lemehov",
note = "RN - ER-292 CN - 295664 AI - FP7 PELGRIMM Project. Deliverable WP3 D3.7 Score = 2",
year = "2015",
month = jun,
day = "3",
language = "English",
volume = "1",
series = "SCK•CEN Reports",
publisher = "SCK CEN",
number = "ER-292",
address = "Belgium",
edition = "1",

}

RIS - Download

TY - BOOK

T1 - Modeling Minor Actinide Bearing Blanket Fuels for Fast-Neutron Reactors

AU - Lemehov, Sergei

N1 - RN - ER-292 CN - 295664 AI - FP7 PELGRIMM Project. Deliverable WP3 D3.7 Score = 2

PY - 2015/6/3

Y1 - 2015/6/3

N2 - MABB fuels have been modeled with the MACROS code with specific interest to americium and neptunium transmutation, fuel swelling and effects of self-irradiation on thermal properties. SUPERFACT-1 rod SF6/SF14 consisting originally of (U,Am,Np)O2 pellets was recalculated. Fission gas release, burnup and transmutation behavior as calculated with the MACROS code are in good agreement with the reported PIE data. Disagreement between calculations and observations was revealed for restructuring and central void formation. PIE data show absence of columnar grains and central void, though there are some indications that under operation conditions fuel was close to onset. Due to low thermal conductivity calculated central temperature was higher than 1800°C providing conditions for the central void formation and restructuring. Further analysis of input data and models will be conducted. Also, code calculations were performed to simulate release of fission helium in conditions of MARIOS irradiation.

AB - MABB fuels have been modeled with the MACROS code with specific interest to americium and neptunium transmutation, fuel swelling and effects of self-irradiation on thermal properties. SUPERFACT-1 rod SF6/SF14 consisting originally of (U,Am,Np)O2 pellets was recalculated. Fission gas release, burnup and transmutation behavior as calculated with the MACROS code are in good agreement with the reported PIE data. Disagreement between calculations and observations was revealed for restructuring and central void formation. PIE data show absence of columnar grains and central void, though there are some indications that under operation conditions fuel was close to onset. Due to low thermal conductivity calculated central temperature was higher than 1800°C providing conditions for the central void formation and restructuring. Further analysis of input data and models will be conducted. Also, code calculations were performed to simulate release of fission helium in conditions of MARIOS irradiation.

KW - Americium

KW - Neptunium

KW - Phenix

KW - MOX

KW - Helium

KW - SUPERFACT

KW - MARINE

KW - MARIOS

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/ezp_139507

M3 - ER - External report

VL - 1

T3 - SCK•CEN Reports

BT - Modeling Minor Actinide Bearing Blanket Fuels for Fast-Neutron Reactors

PB - SCK CEN

ER -

ID: 123288