Fundamental integral cross section ratio measurements in the thermal-neutron-induced uranium-235 fission neutron spectrum

Albert Fabry; J.A. Grundl; C. Eisenhauer

Fundamental integral cross section ratio measurements in the thermal-neutron-induced uranium-235 fission neutron spectrum

Albert Fabry
, J.A. Grundl
, C. Eisenhauer

Research output › peer-review

Abstract

High- accuracy integral cross section ratio measurements have been performed in the thermal- neutron-induced uranium- 235 fission neutron spectrum. This involves the basic fission reactions 235U ( n , f) , 239Pu ( n , f ) , 238U ( n , f ) and 237 Np ( n , f ) ; and the gold capturer and 115 In ( n , n ' )115mIn dosimetry reactions . The uranium- 235 fission neutron spectrum is generated at the center of a
one meter diameter spherical cavity within a graphite thermal column . Simple and variable geometrical arrangements were used and evaluated for neutron field purity . The fission rates
were determined with the NBS double fission chamber as well as with others of different size and design . All fission detectors were validated within a parallel program of interlaboratory comparisons in the MOL- ΣΣ Standard Neutron Field . The activation rates have been measured with calibrated gamma- ray spectrometers . The resulting integral cross section ratios relative to the 238U ( n , f ) reaction are , for PU ( n , f) : 3.94 ± 0.08 ; Pu ( n , f) : 5.93 ± 0.13 ; 237Np ( n , f ) : 4.35 ± 0.13 ; In ( n , n ' )115mIn : 0.620 ± 0.019 and; 197 Au (n, r)198 Au : 0.287 ± 0.014

Original language	English
Title of host publication	Nuclear Cross Sections and Technology: Proceedings of a Conference
Subtitle of host publication	NBS Special publication
Pages	254-257
Number of pages	4
Volume	1
State	Published - 1975

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Fabry, A., Grundl, J. A., & Eisenhauer, C. (1975). Fundamental integral cross section ratio measurements in the thermal-neutron-induced uranium-235 fission neutron spectrum. In Nuclear Cross Sections and Technology: Proceedings of a Conference: NBS Special publication (Vol. 1, pp. 254-257) https://books.google.be/books/about/Nuclear_Cross_Sections_and_Technology.html?id=gtHXrljMM-kC&redir_esc=y

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title = "Fundamental integral cross section ratio measurements in the thermal-neutron-induced uranium-235 fission neutron spectrum",

abstract = "High- accuracy integral cross section ratio measurements have been performed in the thermal- neutron-induced uranium- 235 fission neutron spectrum. This involves the basic fission reactions 235U ( n , f) , 239Pu ( n , f ) , 238U ( n , f ) and 237 Np ( n , f ) ; and the gold capturer and 115 In ( n , n ' )115mIn dosimetry reactions . The uranium- 235 fission neutron spectrum is generated at the center of a one meter diameter spherical cavity within a graphite thermal column . Simple and variable geometrical arrangements were used and evaluated for neutron field purity . The fission rates were determined with the NBS double fission chamber as well as with others of different size and design . All fission detectors were validated within a parallel program of interlaboratory comparisons in the MOL- ΣΣ Standard Neutron Field . The activation rates have been measured with calibrated gamma- ray spectrometers . The resulting integral cross section ratios relative to the 238U ( n , f ) reaction are , for PU ( n , f) : 3.94 ± 0.08 ; Pu ( n , f) : 5.93 ± 0.13 ; 237Np ( n , f ) : 4.35 ± 0.13 ; In ( n , n ' )115mIn : 0.620 ± 0.019 and; 197 Au (n, r)198 Au : 0.287 ± 0.014",

author = "Albert Fabry and J.A. Grundl and C. Eisenhauer",

year = "1975",

language = "English",

volume = "1",

pages = "254--257",

booktitle = "Nuclear Cross Sections and Technology: Proceedings of a Conference",

}

Fabry, A, Grundl, JA & Eisenhauer, C 1975, Fundamental integral cross section ratio measurements in the thermal-neutron-induced uranium-235 fission neutron spectrum. in Nuclear Cross Sections and Technology: Proceedings of a Conference: NBS Special publication. vol. 1, pp. 254-257. <https://books.google.be/books/about/Nuclear_Cross_Sections_and_Technology.html?id=gtHXrljMM-kC&redir_esc=y>

TY - GEN

T1 - Fundamental integral cross section ratio measurements in the thermal-neutron-induced uranium-235 fission neutron spectrum

AU - Fabry, Albert

AU - Grundl, J.A.

AU - Eisenhauer, C.

PY - 1975

Y1 - 1975

N2 - High- accuracy integral cross section ratio measurements have been performed in the thermal- neutron-induced uranium- 235 fission neutron spectrum. This involves the basic fission reactions 235U ( n , f) , 239Pu ( n , f ) , 238U ( n , f ) and 237 Np ( n , f ) ; and the gold capturer and 115 In ( n , n ' )115mIn dosimetry reactions . The uranium- 235 fission neutron spectrum is generated at the center of a one meter diameter spherical cavity within a graphite thermal column . Simple and variable geometrical arrangements were used and evaluated for neutron field purity . The fission rates were determined with the NBS double fission chamber as well as with others of different size and design . All fission detectors were validated within a parallel program of interlaboratory comparisons in the MOL- ΣΣ Standard Neutron Field . The activation rates have been measured with calibrated gamma- ray spectrometers . The resulting integral cross section ratios relative to the 238U ( n , f ) reaction are , for PU ( n , f) : 3.94 ± 0.08 ; Pu ( n , f) : 5.93 ± 0.13 ; 237Np ( n , f ) : 4.35 ± 0.13 ; In ( n , n ' )115mIn : 0.620 ± 0.019 and; 197 Au (n, r)198 Au : 0.287 ± 0.014

AB - High- accuracy integral cross section ratio measurements have been performed in the thermal- neutron-induced uranium- 235 fission neutron spectrum. This involves the basic fission reactions 235U ( n , f) , 239Pu ( n , f ) , 238U ( n , f ) and 237 Np ( n , f ) ; and the gold capturer and 115 In ( n , n ' )115mIn dosimetry reactions . The uranium- 235 fission neutron spectrum is generated at the center of a one meter diameter spherical cavity within a graphite thermal column . Simple and variable geometrical arrangements were used and evaluated for neutron field purity . The fission rates were determined with the NBS double fission chamber as well as with others of different size and design . All fission detectors were validated within a parallel program of interlaboratory comparisons in the MOL- ΣΣ Standard Neutron Field . The activation rates have been measured with calibrated gamma- ray spectrometers . The resulting integral cross section ratios relative to the 238U ( n , f ) reaction are , for PU ( n , f) : 3.94 ± 0.08 ; Pu ( n , f) : 5.93 ± 0.13 ; 237Np ( n , f ) : 4.35 ± 0.13 ; In ( n , n ' )115mIn : 0.620 ± 0.019 and; 197 Au (n, r)198 Au : 0.287 ± 0.014

M3 - In-proceedings paper

VL - 1

SP - 254

EP - 257

BT - Nuclear Cross Sections and Technology: Proceedings of a Conference

ER -