Thermal performances and melting risk assessment in a LMFBR fuel pin

F. Vettraino; P. C. Cacciabue; F. Brunelli

doi:10.1016/0022-3115(85)90304-6

Thermal performances and melting risk assessment in a LMFBR fuel pin

F. Vettraino
, P. C. Cacciabue
, F. Brunelli

Agenzia Nazionale Per Le Nuove Tecnologie
European Commission, Joint Research Centre
General Sytems

Research output: Contribution to journal › Article › peer-review

Abstract

A reliable evaluation of fuel temperature is a key safety requirement in the design of the fuel assembly of a nuclear reactor, especially in the case of a LMFBR whose efficient operation requires high thermal performance fuel.

The physico-chemical properties such as density, oxygen to metal ratio and thermal conductivity of a typical LMFBR mixed-oxide fuel, which are known to change in a remarkable way under irradiation, strongly affect the temperature profile within the fuel pellet.

A statistical analysis of the temperature values in the fuel of the Italian Fast Reactor PEC, has been performed by means of the RSM code (Response Surface Methodology) coupled to a Monte-Carlo Technique (MUP code), in order to demonstrate that the melting risk is substantially negligible.

Original language	English
Pages (from-to)	154-162
Number of pages	9
Journal	Journal of Nuclear Materials
Volume	130
DOIs	https://doi.org/10.1016/0022-3115(85)90304-6
Publication status	Published - Feb 1985
Externally published	Yes

Bibliographical note

Published online date: 24 February 2003

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Cite this

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title = "Thermal performances and melting risk assessment in a LMFBR fuel pin",

abstract = "A reliable evaluation of fuel temperature is a key safety requirement in the design of the fuel assembly of a nuclear reactor, especially in the case of a LMFBR whose efficient operation requires high thermal performance fuel. The physico-chemical properties such as density, oxygen to metal ratio and thermal conductivity of a typical LMFBR mixed-oxide fuel, which are known to change in a remarkable way under irradiation, strongly affect the temperature profile within the fuel pellet. A statistical analysis of the temperature values in the fuel of the Italian Fast Reactor PEC, has been performed by means of the RSM code (Response Surface Methodology) coupled to a Monte-Carlo Technique (MUP code), in order to demonstrate that the melting risk is substantially negligible.",

author = "F. Vettraino and Cacciabue, \{P. C.\} and F. Brunelli",

note = "Published online date: 24 February 2003",

year = "1985",

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doi = "10.1016/0022-3115(85)90304-6",

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volume = "130",

pages = "154--162",

journal = "Journal of Nuclear Materials",

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T1 - Thermal performances and melting risk assessment in a LMFBR fuel pin

AU - Vettraino, F.

AU - Cacciabue, P. C.

AU - Brunelli, F.

N1 - Published online date: 24 February 2003

PY - 1985/2

Y1 - 1985/2

N2 - A reliable evaluation of fuel temperature is a key safety requirement in the design of the fuel assembly of a nuclear reactor, especially in the case of a LMFBR whose efficient operation requires high thermal performance fuel. The physico-chemical properties such as density, oxygen to metal ratio and thermal conductivity of a typical LMFBR mixed-oxide fuel, which are known to change in a remarkable way under irradiation, strongly affect the temperature profile within the fuel pellet. A statistical analysis of the temperature values in the fuel of the Italian Fast Reactor PEC, has been performed by means of the RSM code (Response Surface Methodology) coupled to a Monte-Carlo Technique (MUP code), in order to demonstrate that the melting risk is substantially negligible.

AB - A reliable evaluation of fuel temperature is a key safety requirement in the design of the fuel assembly of a nuclear reactor, especially in the case of a LMFBR whose efficient operation requires high thermal performance fuel. The physico-chemical properties such as density, oxygen to metal ratio and thermal conductivity of a typical LMFBR mixed-oxide fuel, which are known to change in a remarkable way under irradiation, strongly affect the temperature profile within the fuel pellet. A statistical analysis of the temperature values in the fuel of the Italian Fast Reactor PEC, has been performed by means of the RSM code (Response Surface Methodology) coupled to a Monte-Carlo Technique (MUP code), in order to demonstrate that the melting risk is substantially negligible.

U2 - 10.1016/0022-3115(85)90304-6

DO - 10.1016/0022-3115(85)90304-6

M3 - Article

AN - SCOPUS:0021370732

SN - 0022-3115

VL - 130

SP - 154

EP - 162

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

ER -

Thermal performances and melting risk assessment in a LMFBR fuel pin

Abstract

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