The neutron induced fission cross section of 235U in the energy region from 0.008 eV to 30 keV

C. Wagemans; A. J. Deruytter

doi:10.1016/0306-4549(76)90028-1

The neutron induced fission cross section of ²³⁵U in the energy region from 0.008 eV to 30 keV

C. Wagemans
, A. J. Deruytter

Research output › peer-review

Abstract

The neutron induced fission cross-section of ²³⁵U was measured up to 30 keV at a 30 m flight-path of the CBNM Linac. The fission reaction rate and the neutron flux were determined simultaneously with surface barrier detectors placed on each side of back-to-back ²³⁵U and ¹⁰B layers. The fission cross-section was calculated assuming a 1 v-behaviour of the ¹⁰B(n, α)⁷Li cross-section and normalized to ∫^11eV_7.8eV σ_f(E) dE = 240 barn.eV. The average fission cross-section was calculated in several energy regions and compared with other results. Also the fission integral ∫^1000eV_1eV σ_f(E) dE was calculated yielding 16.16 barn.keV; for the epicadmium resonance integral we obtained I_f = 280 ± 7 barn.

Original language	English
Pages (from-to)	437-445
Number of pages	9
Journal	Annals of nuclear energy
Volume	3
Issue number	9-10
DOIs	https://doi.org/10.1016/0306-4549(76)90028-1
State	Published - 1976

ASJC Scopus subject areas

Nuclear Energy and Engineering

Access to Document

10.1016/0306-4549(76)90028-1

Cite this

@article{e0ab163b65b6492d85adf2425a7f032a,

title = "The neutron induced fission cross section of 235U in the energy region from 0.008 eV to 30 keV",

abstract = "The neutron induced fission cross-section of 235U was measured up to 30 keV at a 30 m flight-path of the CBNM Linac. The fission reaction rate and the neutron flux were determined simultaneously with surface barrier detectors placed on each side of back-to-back 235U and 10B layers. The fission cross-section was calculated assuming a 1 v-behaviour of the 10B(n, α)7Li cross-section and normalized to ∫11eV7.8eV σf(E) dE = 240 barn.eV. The average fission cross-section was calculated in several energy regions and compared with other results. Also the fission integral ∫1000eV1eV σf(E) dE was calculated yielding 16.16 barn.keV; for the epicadmium resonance integral we obtained If = 280 ± 7 barn.",

author = "C. Wagemans and Deruytter, \{A. J.\}",

year = "1976",

doi = "10.1016/0306-4549(76)90028-1",

language = "English",

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pages = "437--445",

journal = "Annals of nuclear energy",

issn = "0306-4549",

publisher = "Elsevier Ltd",

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T1 - The neutron induced fission cross section of 235U in the energy region from 0.008 eV to 30 keV

AU - Wagemans, C.

AU - Deruytter, A. J.

PY - 1976

Y1 - 1976

N2 - The neutron induced fission cross-section of 235U was measured up to 30 keV at a 30 m flight-path of the CBNM Linac. The fission reaction rate and the neutron flux were determined simultaneously with surface barrier detectors placed on each side of back-to-back 235U and 10B layers. The fission cross-section was calculated assuming a 1 v-behaviour of the 10B(n, α)7Li cross-section and normalized to ∫11eV7.8eV σf(E) dE = 240 barn.eV. The average fission cross-section was calculated in several energy regions and compared with other results. Also the fission integral ∫1000eV1eV σf(E) dE was calculated yielding 16.16 barn.keV; for the epicadmium resonance integral we obtained If = 280 ± 7 barn.

AB - The neutron induced fission cross-section of 235U was measured up to 30 keV at a 30 m flight-path of the CBNM Linac. The fission reaction rate and the neutron flux were determined simultaneously with surface barrier detectors placed on each side of back-to-back 235U and 10B layers. The fission cross-section was calculated assuming a 1 v-behaviour of the 10B(n, α)7Li cross-section and normalized to ∫11eV7.8eV σf(E) dE = 240 barn.eV. The average fission cross-section was calculated in several energy regions and compared with other results. Also the fission integral ∫1000eV1eV σf(E) dE was calculated yielding 16.16 barn.keV; for the epicadmium resonance integral we obtained If = 280 ± 7 barn.

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DO - 10.1016/0306-4549(76)90028-1

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JO - Annals of nuclear energy

JF - Annals of nuclear energy

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