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Title: Modern fast reactor cross section systems

Abstract

Mainly three problems must be solved in the preparation of a group cross section set for fast reactor calculations. The first step is an evaluation of the basic nuclear data, based on experimental information, systematics, nuclear model calculations and clarifications of discrepancies. The second class of problems relates to the proper definition of group cross sections as stems from an accurate multigroup theory. The third problem concerns the weighting fluxes for the group-averaging of the data. Different group tables types stem from different structures in the flux. With the above consideration in mind, three modern group cross section sets are compared. Some typical fast reactor problems are run with the ABN and YSL sets and the results compared.

Authors:
; ; ;
Publication Date:
Research Org.:
Israel Atomic Energy Commission, Yavne (Israel). Soreq Nuclear Research Center
OSTI Identifier:
4567480
Report Number(s):
IA-1144
NSA Number:
NSA-22-013900
Resource Type:
Conference
Resource Relation:
Conference: International conference on the safety of fast breeder reactors, Aix-en-Provence (France), 19-22 Sep 1967
Country of Publication:
Israel
Language:
English
Subject:
N36100* -Physics (Nuclear)-Neutron Interactions with Matter; CROSS SECTIONS; FAST NEUTRONS; NEUTRON BEAMS; NUCLEAR REACTIONS; PREPARATION; REACTIVITY; REACTORS; NEUTRON CROSS SECTIONS/preparation of multigroup, for fast reactor calculations; REACTORS, FAST/physics calculations for, preparation of multigroup neutron cross sections for

Citation Formats

Yiftah, S., Segev, M., Lemanska, M., and Caner, M. Modern fast reactor cross section systems. Israel: N. p., 1967. Web.
Yiftah, S., Segev, M., Lemanska, M., & Caner, M. Modern fast reactor cross section systems. Israel.
Yiftah, S., Segev, M., Lemanska, M., and Caner, M. Sat . "Modern fast reactor cross section systems". Israel. https://www.osti.gov/servlets/purl/4567480.
@article{osti_4567480,
title = {Modern fast reactor cross section systems},
author = {Yiftah, S. and Segev, M. and Lemanska, M. and Caner, M.},
abstractNote = {Mainly three problems must be solved in the preparation of a group cross section set for fast reactor calculations. The first step is an evaluation of the basic nuclear data, based on experimental information, systematics, nuclear model calculations and clarifications of discrepancies. The second class of problems relates to the proper definition of group cross sections as stems from an accurate multigroup theory. The third problem concerns the weighting fluxes for the group-averaging of the data. Different group tables types stem from different structures in the flux. With the above consideration in mind, three modern group cross section sets are compared. Some typical fast reactor problems are run with the ABN and YSL sets and the results compared.},
doi = {},
journal = {},
number = ,
volume = ,
place = {Israel},
year = {1967},
month = {7}
}

Conference:
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