Multigroup Elastic Scattering Cross Sections for Heavy Elements

Henryson, H.

doi:10.13182/nse71-a21274

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Heavy Elements1

(4)1

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1973

2018

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Cited by 6 publications

(5 citation statements)

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“…For heavy elements which scatter less than four ultrafine groups (i.e., A > 160 for u ∆ = 1/120), the method by Henryson [17] is used. The elastic scattering transfer matrix in Eq.…”

Section: Heavy Elementsmentioning

confidence: 99%

MC²-3: Multigroup Cross Section Generation Code for Fast Reactor Analysis

Lee

Yang

2017

Nuclear Science and Engineering

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“…For heavy elements which scatter less than four ultrafine groups (i.e., A > 160 for u ∆ = 1/120), the method by Henryson [17] is used. The elastic scattering transfer matrix in Eq.…”

Section: Heavy Elementsmentioning

confidence: 99%

MC²-3: Multigroup Cross Section Generation Code for Fast Reactor Analysis

Lee

Yang

2017

Nuclear Science and Engineering

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“…15 Heavy element transfer matrices are calculated semi-analytically according to the methods described in Ref. 17.…”

Section: (4)mentioning

confidence: 99%

ETOE-2/MC/sup 2/-2/SDX multigroup cross-section processing

Toppel¹,

Henryson²,

Stenberg³

1978

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The ETOE-2/MC 2 -2/SDX multigroup cross-section processing codes have been designed to provide a comprehensive neutron cross-section processing capability for a wide range of applications including critical experiment analysis and core design calculations. Fundamental nuclear data from ENDF/B provide the primary input to the code system and the output consists of a user-specified CCCC ISOTXS multigroup cross-section data file, Great flexibility has been provided to the user in specifying the rigor of the calculation so that a unified cross-section processing system with a single data base is available which may be used for both preliminary survey scoping studies and rigorous design calculations.The principal program blocks of the code system include: a library processor and format converter between ENDF/B data and the KC 2 -2/SDX library; an ultra-fine-group fundamental mode calculation (MC 2 -2) which provides a composition dependent spectrum calculation and broad-group collapsing capability; a rigorous hyper-fine-group spatially heterogeneous resolved resonance calculation (RABANL) to supplement the more approximate NR approximation used in the ultra-fine-group treatement; and an intermediate group space-dependent capability (SDX).

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“…The in-group scattering cross-section can be obtained in terms of Equation 5 and the total scattering cross-section, which is given by r us…”

mentioning

confidence: 99%

A Rapid Calculational Method for Multigroup Elastic Transfer

Becker

1974

Nuclear Science and Engineering

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Multigroup Elastic Scattering Cross Sections for Heavy Elements

Cited by 6 publications

References 0 publications

MC²-3: Multigroup Cross Section Generation Code for Fast Reactor Analysis

MC²-3: Multigroup Cross Section Generation Code for Fast Reactor Analysis

ETOE-2/MC/sup 2/-2/SDX multigroup cross-section processing

A Rapid Calculational Method for Multigroup Elastic Transfer

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Multigroup Elastic Scattering Cross Sections for Heavy Elements

Cited by 6 publications

References 0 publications

MC2-3: Multigroup Cross Section Generation Code for Fast Reactor Analysis

MC2-3: Multigroup Cross Section Generation Code for Fast Reactor Analysis

ETOE-2/MC/sup 2/-2/SDX multigroup cross-section processing

A Rapid Calculational Method for Multigroup Elastic Transfer

Contact Info

Product

Resources

About

MC²-3: Multigroup Cross Section Generation Code for Fast Reactor Analysis

MC²-3: Multigroup Cross Section Generation Code for Fast Reactor Analysis