Measurement of flux tilt and eigenvalue separation in axially decoupled core
- 1. Nagoya Univ. (Japan). School of Engineering
Description
A study on the nuclear characteristics of an axially decoupled core was performed through a series of experiments using the solid moderator core in the Kyoto University Critical Assembly (KUCA). In the axially decoupled core which has an internal blanket between the upper and lower cores, the measured differential reactivity worth of a control rod moving axially was apparently asymmetric between the two core regions. Since it was considered that this phenomenon was attributed to the neutron flux tilt caused by the axial movement of control rods during the measurement of differential worth, the axial reaction rate distributions were measured by gold wires with and without a cadmium tube. It was found that the reaction rate distribution was remarkably tilted by changing the pattern of control rods inserted in the core to maintain the critical state, and that the flux distribution was tilted without energy dependency. The value of first-order eigenvalue separation was obtained using the relation between the neutron flux tilt and the first-mode eigenvalue separation based on the Explicit Higher-order Perturbation (EHP) method. This value agreed with the calculated result by the SRAC system. (author)
Additional details
Publishing Information
- Journal Title
- Journal of Nuclear Science and Technology (Tokyo)
- Journal Volume
- 34
- Journal Issue
- 5
- Journal Page Range
- p. 445-453.
- ISSN
- 0022-3131
- CODEN
- JNSTAX
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 28064908
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CONTROL ROD WORTHS; DISTRIBUTION; EIGENVALUES; GOLD; HETEROGENEOUS REACTOR CORES; KUCA REACTOR; NEUTRON FLUX TILTING; REACTION KINETICS; REACTOR KINETICS; WIRES
- Descriptors DEC
- ELEMENTS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; GRAPHITE MODERATED REACTORS; KINETICS; METALS; REACTOR COMPONENTS; REACTOR CORES; REACTORS; RESEARCH AND TEST REACTORS; TRANSITION ELEMENTS; WATER MODERATED REACTORS; ZERO POWER REACTORS