| dc.creator | CASTRO, ALFREDO J.A. | |
| dc.creator | SCURO, NIKOLAS L. | |
| dc.creator | ANDRADE, DELVONEI A. | |
| dc.creator | INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE | |
| dc.date | 2018-01-03T10:40:58Z | |
| dc.date | 2018-01-03T10:40:58Z | |
| dc.date | October 22-27, 2017 | |
| dc.date.accessioned | 2023-09-28T14:05:07Z | |
| dc.date.available | 2023-09-28T14:05:07Z | |
| dc.identifier | http://repositorio.ipen.br/handle/123456789/28204 | |
| dc.identifier.uri | https://repositorioslatinoamericanos.uchile.cl/handle/2250/8998458 | |
| dc.description | The fuel elements of a MTR (Material Testing Reactor) type nuclear reactor are mostly composed of aluminumcoated
fuel plates containing the core of uranium silica (U3Si2) dispersed in an aluminum matrix. These plates
have a thickness of the order of millimeters and are much longer in relation to their thickness. They are arranged
in parallel in the assembly of the fuel element to form channels between them a few millimeters in thickness,
through which there is a flow of the coolant. This configuration, combined with the need for a flow at high flow
rates to ensure the cooling of the fuel element in operation, may create problems of mechanical failure of fuel
plate due to the vibration induced by the flow in the channels. In the case of critical velocity excessive
permanent deflections of the plates can cause blockage of the flow channel in the reactor core and lead to
overheating in the plates. For this study an experimental bench capable of high volume flows and a test section
that simulates a plate-like fuel element with three cooling channels were developed. The dimensions of the test
section were based on the dimensions of the Fuel Element of the Brazilian Multipurpose Reactor (RMB), whose
project is being coordinated by the National Commission of Nuclear Energy (CNEN). The experiments
performed attained the objective of reaching Miller's critical velocity condition. The critical velocity was
reached with 14.5 m/s leading to the consequent plastic deformation of the flow channel plates. | |
| dc.publisher | Associa????o Brasileira de Energia Nuclear | |
| dc.rights | openAccess | |
| dc.subject | critical velocity | |
| dc.subject | deformation | |
| dc.subject | experimental data | |
| dc.subject | fluid flow | |
| dc.subject | fuel assemblies | |
| dc.subject | fuel plates | |
| dc.subject | mtr reactor | |
| dc.subject | nuclear fuels | |
| dc.subject | reactor cores | |
| dc.title | Experimental investigation of critical velocity in a parallel plate research reactor fuel assembly | |
| dc.type | Texto completo de evento | |
| dc.coverage | I | |
| dc.local | Rio de Janeiro, RJ | |
