Evaluation of the BR3 third core vessel steel specimens

P. De Meester; Philippe Van Asbroeck; José Van de Velde; Constantinus Van Loon; L. Laurent

Evaluation of the BR3 third core vessel steel specimens

P. De Meester
, Philippe Van Asbroeck
, José Van de Velde
, Constantinus Van Loon
, L. Laurent

Research output › peer-review

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Abstract

Second and third core pressure vessel steel samples have been tested after irradiation. The shift in N.D.T. -30 fr-lb. for samples being irradiated for an integrated dose up to 8.5 * 10²⁰ nvt is 305° C. Considering the sample positions, it can be concluded that in the BR3 vessel after Vulcain core 2bis, brittleness could occur from the temperature range 60 - 95°C, and after Vulcain core 3 from the temperature range 70 - 100* C. It should therefore be preferable to avoid high pressure and specially sharp pressure transients even at relatively lo« absolute pressures, below that given temperature range increased by a safety factor.

Original language	English
Publisher	SCK CEN
Number of pages	22
State	Published - Jul 1971

Publication series

Name	SCK CEN Reports
Publisher	SCK CEN
No.	BLG-459

Access to Document

BLG-459Final published version, 7.73 MBLicense: Unspecified

Cite this

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title = "Evaluation of the BR3 third core vessel steel specimens",

abstract = "Second and third core pressure vessel steel samples have been tested after irradiation. The shift in N.D.T. -30 fr-lb. for samples being irradiated for an integrated dose up to 8.5 * 1020 nvt is 305° C. Considering the sample positions, it can be concluded that in the BR3 vessel after Vulcain core 2bis, brittleness could occur from the temperature range 60 - 95°C, and after Vulcain core 3 from the temperature range 70 - 100* C. It should therefore be preferable to avoid high pressure and specially sharp pressure transients even at relatively lo« absolute pressures, below that given temperature range increased by a safety factor.",

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AU - De Meester, P.

AU - Van Asbroeck, Philippe

AU - Van de Velde, José

AU - Van Loon, Constantinus

AU - Laurent, L.

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Y1 - 1971/7

N2 - Second and third core pressure vessel steel samples have been tested after irradiation. The shift in N.D.T. -30 fr-lb. for samples being irradiated for an integrated dose up to 8.5 * 1020 nvt is 305° C. Considering the sample positions, it can be concluded that in the BR3 vessel after Vulcain core 2bis, brittleness could occur from the temperature range 60 - 95°C, and after Vulcain core 3 from the temperature range 70 - 100* C. It should therefore be preferable to avoid high pressure and specially sharp pressure transients even at relatively lo« absolute pressures, below that given temperature range increased by a safety factor.

AB - Second and third core pressure vessel steel samples have been tested after irradiation. The shift in N.D.T. -30 fr-lb. for samples being irradiated for an integrated dose up to 8.5 * 1020 nvt is 305° C. Considering the sample positions, it can be concluded that in the BR3 vessel after Vulcain core 2bis, brittleness could occur from the temperature range 60 - 95°C, and after Vulcain core 3 from the temperature range 70 - 100* C. It should therefore be preferable to avoid high pressure and specially sharp pressure transients even at relatively lo« absolute pressures, below that given temperature range increased by a safety factor.

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