Characteristics of the thermal-neutron field in the experimental channel of a pulsed graphite reactor

Citation
Nv. Gorin et al., Characteristics of the thermal-neutron field in the experimental channel of a pulsed graphite reactor, ATOM ENERGY, 90(4), 2001, pp. 261-266
Citations number
7
Categorie Soggetti
Nuclear Emgineering
Journal title
ATOMIC ENERGY
ISSN journal
10634258 → ACNP
Volume
90
Issue
4
Year of publication
2001
Pages
261 - 266
Database
ISI
SICI code
1063-4258(200104)90:4<261:COTTFI>2.0.ZU;2-7
Abstract
The current of the sensitive sections of a five-section Compton emission ne utron detector which are placed at different levels in the vertical directi on in the central experimental channel of a pulsed graphite reactor during a regulatable pulse that heats the reactor fuel up to 1400 K was measured. It was established that the shape of the thermal-neutron distribution over the channel height changes during a run:for room-temperature fuel the distr ibution maximum lies near the center level in the core. As the fuel tempera ture increases to 550 K and the control rods are extracted, the maximum shi fts downwards by approximately 13 cm and with further heating of the fuel u p to similar to 1400 K, the maximum returns to the center level when the co ntrol rods are extracted. 3 figures, 2 tables, 7 references.