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A Monte Carlo program for calculating high energy spectra in cylindrical geometry on the IBM 709 computer

Technical Report:

Abstract

The report describes an I.B.M. 709 program written at the request of the Reactor Division, Harwell, to obtain high energy spectra in a system containing a number of fissile and non-fissile materials, arranged as concentric cylinders of infinite length surrounded by an outer material with a square or rectangular boundary. At the cell boundary neutrons can be lost by leakage or reflected back into the system. A specified number of fission neutrons born in the fissile materials, together with any descendants they may have, are tracked one by one through the system until they are absorbed, lost by leakage through the lattice boundary, or their energies have fallen below a specifiable cut-off energy. The neutrons may be started from anywhere in the system and all neutron-nucleus reactions that occur in the nuclides supplied with the program are allowed. A descriptions is given of the use of the program, the current version of which is available as a self-loading binary tape which contains, in addition to the program, all the nuclear data at present available. Binary card decks are also available and nuclear data for other nuclides can be added. A feature of the program is the flexibility with which the  More>>
Authors:
Francescon, S [1] 
  1. Computer Branch, Technical Assessments and Services Division, Atomic Energy Establishment, Winfrith, Dorchester, Dorset (United Kingdom)
Publication Date:
Oct 15, 1960
Product Type:
Technical Report
Report Number:
AEEW-R-45
Resource Relation:
Other Information: Country of input: International Atomic Energy Agency (IAEA); 4 refs, 4 figs, 6 tabs
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; COMPUTER PROGRAM DOCUMENTATION; COMPUTERS; CYLINDERS; CYLINDRICAL CONFIGURATION; ENERGY SPECTRA; FISSILE MATERIALS; FISSION NEUTRONS; GEOMETRY; HEAVY WATER; ISOTOPES; LEAKS; MONTE CARLO METHOD; RADIATION EFFECTS; SPATIAL DISTRIBUTION; URANIUM
OSTI ID:
20885106
Research Organizations:
United Kingdom Atomic Energy Authority, Reactor Group, Winfrith (United Kingdom)
Country of Origin:
United Kingdom
Language:
English
Other Identifying Numbers:
TRN: GB07A0191050577
Availability:
Available from INIS in electronic form; Also available from H.M. Stationery Office
Submitting Site:
GBN
Size:
28 pages
Announcement Date:
Jul 16, 2007

Technical Report:

Citation Formats

Francescon, S. A Monte Carlo program for calculating high energy spectra in cylindrical geometry on the IBM 709 computer. United Kingdom: N. p., 1960. Web.
Francescon, S. A Monte Carlo program for calculating high energy spectra in cylindrical geometry on the IBM 709 computer. United Kingdom.
Francescon, S. 1960. "A Monte Carlo program for calculating high energy spectra in cylindrical geometry on the IBM 709 computer." United Kingdom.
@misc{etde_20885106,
title = {A Monte Carlo program for calculating high energy spectra in cylindrical geometry on the IBM 709 computer}
author = {Francescon, S}
abstractNote = {The report describes an I.B.M. 709 program written at the request of the Reactor Division, Harwell, to obtain high energy spectra in a system containing a number of fissile and non-fissile materials, arranged as concentric cylinders of infinite length surrounded by an outer material with a square or rectangular boundary. At the cell boundary neutrons can be lost by leakage or reflected back into the system. A specified number of fission neutrons born in the fissile materials, together with any descendants they may have, are tracked one by one through the system until they are absorbed, lost by leakage through the lattice boundary, or their energies have fallen below a specifiable cut-off energy. The neutrons may be started from anywhere in the system and all neutron-nucleus reactions that occur in the nuclides supplied with the program are allowed. A descriptions is given of the use of the program, the current version of which is available as a self-loading binary tape which contains, in addition to the program, all the nuclear data at present available. Binary card decks are also available and nuclear data for other nuclides can be added. A feature of the program is the flexibility with which the core storage available for input and output data can be allocated according to the requirements of the problem. The output of the program is in the form of a Binary Coded Decimal tape (B.C.D.) which can be used on the normal I.B.M. off-line equipment to print out the results. An example is given of the results obtained for use in radiation damage calculations of the spatial distribution of neutrons in a simple uranium-D{sub 2}O system.}
place = {United Kingdom}
year = {1960}
month = {Oct}
}