An Assessment of ORNL PIE Capabilities for the AGR Program Capsule Post Irradiation Examination
Description
ORNL has facilities and experienced staff that can execute the Advanced Gas Reactor (AGR) Post Irradiation Examination (PIE) task. While the specific PIE breakdown needs to be more formally defined, the basic outline is clear and the existing capabilities can be assessed within the needs of the tasks defined in the program plan. A one-to-one correspondence between the program plan tasks and the current ORNL PIE status was conducted and while some shortcomings were identified, the general capability is available. Specific upgrade needs were identified and reviewed. A path forward was formulated. Building 3525 is available for this work and this building is currently receiving renewed attention from management so that it will be in good working order prior to the expected PIE start date. This building is equipped with the tools necessary for PIEs of this nature, but the long hiatus in coated particle fuel work has left it with aging analysis tools. This report identified several of these tools and rough estimates of what would be required to update and replace them. In addition, other ORNL buildings are available to support Building 3525 in specialized tasks along with the normal laboratory infrastructure. Before the AGR management embarks on any equipment development effort, the PIE tasks should be updated against current program (modeling and data) needs and better defined so that the items to be measured, their measurement uncertainties, and thru-put needs can be reviewed. A Data Task Matrix (DTM) should be prepared so that the program data needs can be compared against the identified PIE tasks and what is practical in the hot cell environment to make sure nothing is overlooked. Finally, thought should be given to the development of standardized equipment designs between sites to avoid redundant design efforts and different measurement techniques. This is a potentially cost saving effort that can also avoid data inconsistencies.
Additional details
Identifiers
Publishing Information
- Imprint Pagination
- vp.
- Report number
- ORNL/TM--2006/526
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 39084692
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- AGR TYPE REACTORS; MEASURING INSTRUMENTS; MODIFICATIONS; ORNL; PLANNING; POST-IRRADIATION EXAMINATION
- Descriptors DEC
- ENRICHED URANIUM REACTORS; GAS COOLED REACTORS; GCR TYPE REACTORS; GRAPHITE MODERATED REACTORS; NATIONAL ORGANIZATIONS; REACTORS; US AEC; US DOE; US ERDA; US ORGANIZATIONS
Optional Information
- Contract/Grant/Project number
- AF3610200; NEAF260; AC05-00OR22725
- Notes
- doi 10.2172/932606
- Funding organization
- NE USDOE - Office of Nuclear Energy (United States)