FASPEC, a program to determine group constants for up to 47 groups in a fast neutron spectrum

Simple item page
dc.contributor.authorSeth, Ernest L.en
dc.contributor.committeechairParkinson, Thomas F.en
dc.contributor.committeememberThomas, James R. Jr.en
dc.contributor.committeememberEdlund, M. C.en
dc.contributor.departmentNuclear Science and Engineeringen
dc.date.accessioned2014-03-14T21:49:35Zen
dc.date.adate2012-11-14en
dc.date.available2014-03-14T21:49:35Zen
dc.date.issued1985-08-05en
dc.date.rdate2012-11-14en
dc.date.sdate2012-11-14en
dc.description.abstractIn reactor core design, a gap exists between the manual calculation of few-group constants and the many-group calculation, by large computer programs. A method is needed by which group constants may be calculated easily and quickly. The FASPEC program is designed to reduce the amount of manual calculation and to complement the large program by reducing the number of times the large program must be run to achieve desired results. The program calculates group constants from 940 microgroups, collapsing to any user-specified number of macrogroups up to 47. FASPEC is based on group-averaged flux calculations by a solution of the Infinite medium neutron transport equation. Flux contributions from inelastic scatter are included while those from neutron up-scatter are not. The energy spectrum considered is from 10 MeV to 0.625 eV. Required input is the atomic number density of each isotope, the number of macrogroups desired and the upper and lower microgroup numbers of each macrogroup. Input is facilitated by prompting in each case. Cross section look-up tables were provided by the Very Improved Monte Carlo code (VIM) for a mid-range Infinite hexagonal lattice. Self-shielding effects are included indirectly. A brief user's guide is provided. Group constants calculated and stored for either terminal display or printed output are group number, lowest energy of the group, macroscopic removal cross section, macroscopic absorption cross section, diffusion coefficient, flux, macroscopic fission cross section, v, the average number of neutrons emitted per fission, and vΣ<sub>f</sub>.en
dc.description.degreeMaster of Scienceen
dc.format.extentv, 108 leavesen
dc.format.mediumBTDen
dc.format.mimetypeapplication/pdfen
dc.identifier.otheretd-11142012-040203en
dc.identifier.sourceurlhttp://scholar.lib.vt.edu/theses/available/etd-11142012-040203/en
dc.identifier.urihttp://hdl.handle.net/10919/45665en
dc.publisherVirginia Techen
dc.relation.haspartLD5655.V855_1985.S474.pdfen
dc.relation.isformatofOCLC# 13098984en
dc.rightsIn Copyrighten
dc.rights.urihttp://rightsstatements.org/vocab/InC/1.0/en
dc.subject.lccLD5655.V855 1985.S474en
dc.subject.lcshNeutron transport theoryen
dc.subject.lcshNuclear reactors -- Data processingen
dc.subject.lcshNuclear reactors -- Design and construction -- Data processingen
dc.titleFASPEC, a program to determine group constants for up to 47 groups in a fast neutron spectrumen
dc.typeThesisen
dc.type.dcmitypeTexten
thesis.degree.disciplineNuclear Science and Engineeringen
thesis.degree.grantorVirginia Polytechnic Institute and State Universityen
thesis.degree.levelmastersen
thesis.degree.nameMaster of Scienceen

Files

Original bundle
Now showing 1 - 1 of 1
Thumbnail Image
Name:
LD5655.V855_1985.S474.pdf
Size:
3.37 MB
Format:
Adobe Portable Document Format
Description:
Download

Collections

Masters Theses