Extended tests on fuel behavior in Reactivity Initiated Accidents type were carried out in the Annular Core Pulse Reactor (ACPR). The tests were performed in a specially designed capsule filled with 7 liters of water at atmospheric pressure and at temperature of 25 C. The fuel specimen is of CANDU design with 10 fuel pellets and 10% U235 enrichment. The tests aimed to establish the clad failure threshold. Over 40 tests were carried out. The fuel behavior during the transient was modeled with the RELAP5-SCDAP computer code. Clad temperatures recorded during the tests were compared with clad temperatures predicted by the RELAP-SCDAP code. Some tests in ACPR in RIA conditions are presented. The paper includes recorded temperatures compared with the RELAP-SCDAP calculations, as well as the RELAP SCDAP models. Put abstract text here.
- Nuclear Engineering Division
RELAP5-SCDAP RIA Type Tests Model
- Views Icon Views
- Share Icon Share
- Search Site
Negut, G, Prisecaru, I, & Danila, N. "RELAP5-SCDAP RIA Type Tests Model." Proceedings of the 14th International Conference on Nuclear Engineering. Volume 3: Structural Integrity; Nuclear Engineering Advances; Next Generation Systems; Near Term Deployment and Promotion of Nuclear Energy. Miami, Florida, USA. July 17–20, 2006. pp. 23-30. ASME. https://doi.org/10.1115/ICONE14-89063
Download citation file: