An unresolved resonance evaluation for235U

L. C. Leal; H. Derrien; N. M. Larson

An unresolved resonance evaluation for²³⁵U

L. C. Leal
, H. Derrien
, N. M. Larson

Nuclear Data

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

1 Scopus citations

Abstract

This paper discusses the resonance evaluation of the ²³⁵U cross sections in the unresolved resonance region from 2.25 keV up to 25 keV and its use in benchmark calculations for criticality safety applications. A criticality safety calculation for a nuclear system with an energy spectrum that peaks in the intermediate energy region requires accurate neutron cross sections in both the resolved and the unresolved resonance regions. A resolved resonance region evaluation of the ²³⁵U cross section was performed in the 1990s, and the evaluation has greatly improved results of benchmark calculations. ¹⁾ Average values of the Reich-Moore resonance parameters obtained in the resolved region were used to initiate a new resonance evaluation of the ²³⁵U cross sections in the unresolved resonance region. The experimental data used in the analysis consisted of high-resolution transmission data, plus fission and capture cross-section data measured at the Oak Ridge Electron Linear Accelerator (ORELA). The evaluation was performed using the computer code SAMMY, which incorporates a methodology for data evaluation in the unresolved resonance region.

Original language	English
Title of host publication	Proceedings of the PHYSOR 2004
Subtitle of host publication	The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments
Pages	1961-1969
Number of pages	9
State	Published - 2004
Event	PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments - Chicago, IL, United States Duration: Apr 25 2004 → Apr 29 2004

Publication series

Name	Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments

Conference

Conference	PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments
Country/Territory	United States
City	Chicago, IL
Period	04/25/04 → 04/29/04

Keywords

Data evaluation
Neutron cross section
Unresolved energy region

Cite this

@inproceedings{efdf586691bf4f24911f74310e973f58,

title = "An unresolved resonance evaluation for235U",

abstract = "This paper discusses the resonance evaluation of the 235U cross sections in the unresolved resonance region from 2.25 keV up to 25 keV and its use in benchmark calculations for criticality safety applications. A criticality safety calculation for a nuclear system with an energy spectrum that peaks in the intermediate energy region requires accurate neutron cross sections in both the resolved and the unresolved resonance regions. A resolved resonance region evaluation of the 235U cross section was performed in the 1990s, and the evaluation has greatly improved results of benchmark calculations. 1) Average values of the Reich-Moore resonance parameters obtained in the resolved region were used to initiate a new resonance evaluation of the 235U cross sections in the unresolved resonance region. The experimental data used in the analysis consisted of high-resolution transmission data, plus fission and capture cross-section data measured at the Oak Ridge Electron Linear Accelerator (ORELA). The evaluation was performed using the computer code SAMMY, which incorporates a methodology for data evaluation in the unresolved resonance region.",

keywords = "Data evaluation, Neutron cross section, Unresolved energy region",

author = "Leal, \{L. C.\} and H. Derrien and Larson, \{N. M.\}",

year = "2004",

language = "English",

isbn = "0894486837",

series = "Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments",

pages = "1961--1969",

booktitle = "Proceedings of the PHYSOR 2004",

note = "PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments ; Conference date: 25-04-2004 Through 29-04-2004",

}

Leal, LC, Derrien, H & Larson, NM 2004, An unresolved resonance evaluation for²³⁵U. in Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments. Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments, pp. 1961-1969, PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments, Chicago, IL, United States, 04/25/04.

An unresolved resonance evaluation for²³⁵U. / Leal, L. C.; Derrien, H.; Larson, N. M.
Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments. 2004. p. 1961-1969 (Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

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N2 - This paper discusses the resonance evaluation of the 235U cross sections in the unresolved resonance region from 2.25 keV up to 25 keV and its use in benchmark calculations for criticality safety applications. A criticality safety calculation for a nuclear system with an energy spectrum that peaks in the intermediate energy region requires accurate neutron cross sections in both the resolved and the unresolved resonance regions. A resolved resonance region evaluation of the 235U cross section was performed in the 1990s, and the evaluation has greatly improved results of benchmark calculations. 1) Average values of the Reich-Moore resonance parameters obtained in the resolved region were used to initiate a new resonance evaluation of the 235U cross sections in the unresolved resonance region. The experimental data used in the analysis consisted of high-resolution transmission data, plus fission and capture cross-section data measured at the Oak Ridge Electron Linear Accelerator (ORELA). The evaluation was performed using the computer code SAMMY, which incorporates a methodology for data evaluation in the unresolved resonance region.

AB - This paper discusses the resonance evaluation of the 235U cross sections in the unresolved resonance region from 2.25 keV up to 25 keV and its use in benchmark calculations for criticality safety applications. A criticality safety calculation for a nuclear system with an energy spectrum that peaks in the intermediate energy region requires accurate neutron cross sections in both the resolved and the unresolved resonance regions. A resolved resonance region evaluation of the 235U cross section was performed in the 1990s, and the evaluation has greatly improved results of benchmark calculations. 1) Average values of the Reich-Moore resonance parameters obtained in the resolved region were used to initiate a new resonance evaluation of the 235U cross sections in the unresolved resonance region. The experimental data used in the analysis consisted of high-resolution transmission data, plus fission and capture cross-section data measured at the Oak Ridge Electron Linear Accelerator (ORELA). The evaluation was performed using the computer code SAMMY, which incorporates a methodology for data evaluation in the unresolved resonance region.

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KW - Neutron cross section

KW - Unresolved energy region

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