Author: R. J. ChenierPublisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Post-irradiation examination procedures document. visual examination of irradiated fuel, control and other rod-type components
Author: R. J. ChenierPublisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Post-irradiation examination procedures document. procedures for the puncturing of fuel rods, collection of fission gases, and void volume determination using the fcv1000
Author: J. MontinPublisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Nondestructive Post-irradiation Examination of Loop-1, S1 and B1 Rods
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
As a part of the Pacific Northwest National Laboratory's Tritium Target Development Program, eleven tritium target rods were irradiated in the Advanced Test Reactor located at the Idaho National Engineering and Environmental Laboratory during 1991. Both nondestructive and destructive post-irradiation examination on all eleven rods was planned under the Tritium Target Development Program. Funding for the program was reduced in 1991 resulting in the early removal of the program experiments before reaching their irradiation goals. Post-irradiation examination was only performed on one of the irradiated rods at the Pacific Northwest National Laboratory before the program was terminated in 1992. On December 6, 1995, the Secretary of Energy announced the pursuit of the Commercial Light-Water Reactor option for producing tritium establishing the Tritium Target Qualification Program at the Pacific Northwest National Laboratory. This program decided to pursue nondestructive and destructive post-irradiation examination of the ten remaining rods from the previous program. The ten rods comprise three experiments. The Loop-1 experiment irradiated eight target rods in a loop configuration for 217 irradiation days. The other two rods were irradiated in two separate irradiation experiments, designated as S1 and B1 for 143 effective full-power days, but at different power levels. After the ten rods were transferred from the ATR Canal to the Hot Fuels Examination Facility, the following examinations were performed: (1) visual examination and photography; (2) neutron radiography; (3) axial gamma scanning; (4) contact profilometry measurement; (5) bow and length measurements; (6) rod puncture and plenum gas analysis/measurement of plenum gas quantity; (7) void volume determination; and (8) internal pressure determination. This report presents the data collected during these examinations.
Post-irradiation examination procedures document. scanning of nuclear fuel rods for gross and isotopic gamma activity
Author: R. R. ElderPublisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Post-irradiation examination procedures document. receiving and identification of full-length LWR fuel rods in universal cell-3
Author: R. J. ChenierPublisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Post-irradiation examination procedures document. marking and sectioning of full-length LWR fuel rods
Author: R. J. ChenierPublisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Post-irradiation Examination Techniques for Research Reactor Fuels
Author: IAEAPublisher: International Atomic Energy Agency
ISBN: 920102021X
Category : Technology & Engineering
Languages : en
Pages : 149
Book Description
Post-irradiation examination (PIE) is an indispensable step in the selection of new or improved research reactor fuel, and in the characterization and understanding of its in-core behaviour. This publication provides an introduction to PIE techniques. It describes a typical PIE process from intercycle inspections in the reactor pool or channel, to hot cell PIE, which is subdivided into non-destructive and destructive testing techniques with their typical output, advantages and drawbacks, and their applicability to understanding fuel irradiation behaviour. Much of the work presented in this publication originated from the research and development of new low enriched uranium research reactor fuels. Intended readers include research reactor operators, regulators and their technical support organizations, fuel developers and manufacturers, laboratory staff, and policy makers.
Post-irradiation examination procedures document. helium leak testing of nuclear fuel rods
Author: R. J. ChenierPublisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Postirradiation Examination Results for the Irradiation Effects Test Series IE-ST-2, Rod IE-002. [PWR].
![Postirradiation Examination Results for the Irradiation Effects Test Series IE-ST-2, Rod IE-002. [PWR]. PDF](https://books.google.com/books/content/images/frontcover/Txz2wQEACAAJ?fife=w80-h100)
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
A postirradiation examination was conducted on a zircaloy-clad, UO2-fueled, pressurized water reactor (PWR) type rod which had been tested in the Power Burst Facility as part of the Irradiation Effects Test Series of the Thermal Fuels Behavior Program. The fuel rod, previously irradiated to a burnup of 15,800 MWd/t was subjected to a power ramp from 28 to 55 kW/m peak power at an average ramp rate of 4 kW/m/min. Posttest fuel restructuring and relocation, fission product redistribution, and fuel rod cladding deformation were evaluated and analyzed.
Post-irradiation examination procedures document.tensile testing of fuel sheathing
Author: D. S. CarterPublisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
