ETOE-2/MC/sup 2/-2/SDX multigroup cross-section processing
The ETOE-2/MC/sup 2/-2/SDX multigroup cross-section processing codes were 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 is provided to the user in specifying the rigor of the calculation, so that a unified cross-section processing system with a single data base which may be used for both preliminary survey scoping studies and rigorous design calculations is available. The principal program blocks of the code system include a library processor and format converter between ENDF/B data and the MC/sup 2/-2/SDX library; an ultra-fine-group fundamental-mode calculation (MC/sup 2/-2) which provides a composition-dependent spectrum calculation and broad-group collapsing capability; a rigorous hyper-fine-group, spatially hetegeneous resolved resonance calculation (RABANL) to supplement the more approximate NR approximation used in the ultra-fine-group treatment; and an intermediate group space-dependent capability (SDX). 5 figures, 4 tables.
- Research Organization:
- Argonne National Lab., Ill. (USA)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6750765
- Report Number(s):
- CONF-780334--5
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
220100 -- Nuclear Reactor Technology-- Theory & Calculation
654003* -- Radiation & Shielding Physics-- Neutron Interactions with Matter
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
COMPUTER CODES
CROSS SECTIONS
DATA PROCESSING
E CODES
KINETICS
M CODES
MULTIGROUP THEORY
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT
NEUTRON TRANSPORT THEORY
PROCESSING
RADIATION TRANSPORT
REACTOR KINETICS
S CODES
TRANSPORT THEORY