Published November 1997 | Version v1
Journal article Metadata-only

Xenon poisoning method for the determination of the average thermal neutron flux, macroscopic fission and total absorption cross sections

Creators

  • 1. Istanbul Technical Univ. (Turkey). Inst. for Nuclear Energy

Description

The paper presents the xenon poisoning method as an experimental way to determine the average thermal neutron flux (anti φ), the average macroscopic fission cross section (anti Σf) and the average total macroscopic absorption cross section (anti Σa) together with the reactivity change due to the 135Xe poisoning. The predictions for the reactivity change due to the 135Xe poisoning are in good agreement with the results of the experiments. The results of anti φ, anti Σf and anti Σa obtained by using the xenon poisoning method are also in satisfactorily agreement with the predictions of TRIGAP and WIMS-D/4 computer codes. The temperature coefficients of the reactivity for the fuel and tank water have also been determined experimentally during this study. (orig.)

Abstract (German)

Die Xenon-Vergiftungsmethode wird als Verfahren vorgestellt, um den durchschnittlichen thermischen Neutronenfluss (anti φ), den makroskopischen Spaltquerschnitt (anti Σf) und den totalen makroskopischen Absorptionsquerschnitt (anti Σa) sowie die Aenderung der Reaktivitaet aufgrund der 135Xe-Vergiftung zu bestimmen. Die Voraussagen fuer die Reaktivitaetsaenderung durch Vergiftung sind in guter Uebereinstimmung mit Rechnungen und der Verwendung der TRIGAP- und WIMS-D/4-Codes. Es wurden auch die Temperaturkoeffizienten der Reaktivitaet fuer Brennstoff und Tankwasser experimentell bestimmt. (orig.)

Additional details

Publishing Information

Journal Title
Kerntechnik (1987)
Journal Volume
62
Journal Issue
5-6
Journal Page Range
p. 245-248.
ISSN
0932-3902
CODEN
KERNEU

INIS

Country of Publication
Germany
Country of Input or Organization
Germany
INIS RN
29019173
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
FISSION; NEUTRON FLUX; REACTIVITY; REACTOR KINETICS; TEMPERATURE COEFFICIENT; TOTAL CROSS SECTIONS; TRIGA TYPE REACTORS; TURKEY; XENON OSCILLATIONS; XENON 135
Descriptors DEC
ASIA; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CROSS SECTIONS; DEVELOPING COUNTRIES; ENRICHED URANIUM REACTORS; EVEN-ODD NUCLEI; HOMOGENEOUS REACTORS; HOURS LIVING RADIOISOTOPES; HYDRIDE MODERATED REACTORS; INTERMEDIATE MASS NUCLEI; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; KINETICS; MIDDLE EAST; MINUTES LIVING RADIOISOTOPES; NUCLEAR REACTIONS; NUCLEI; POISONING; RADIATION FLUX; RADIOISOTOPES; REACTIVITY COEFFICIENTS; REACTORS; RESEARCH AND TEST REACTORS; SOLID HOMOGENEOUS REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; XENON ISOTOPES