Analysis of the E7 CABRI experiment, a structured top transient in restrained conditions, with SAS-SFR code
Creators
- 1. Institute for Neutron Physics and Reactor Technology, Karlsruhe Institute of Technology, Eggenstein-Leopoldshafen (Germany)
Description
The CABRI E7 experiment was performed to study fuel pin failure and post-failure phenomena for an industrial pin with annular fuel pellet design and pin rupture with subsequent fuel ejection into liquid sodium. E7 used a structured Transient OverPower (TOP) starting at nominal cooling conditions leading to mechanical pin failure due to cavity pressure build-up at still constrained clad conditions. In this work we have studied the failure mechanisms and failure conditions serving as boundary conditions for the post-failure material-relocation behavior. We have also evaluated SAS-SFR code's capabilities to simulate post-failure phenomena in view of experimental results. We present comparisons of measured results with SAS-SFR results for the power operation irradiation of the fuel pin as well as for the E7 failure and post-failure behavior. (author)
Additional details
Publishing Information
- Imprint Title
- Proceedings of the 23th international conference on nuclear engineering (ICONE-23)
- Imprint Pagination
- [3737 p.]
- Journal Page Range
- [9 p.]
Conference
- Title
- 23. international conference on nuclear engineering
- Acronym
- ICONE-23
- Dates
- 17-21 May 2015
- Place
- Chiba (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 48027448
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CABRI REACTOR; FISSION PRODUCT RELEASE; FUEL PELLETS; FUEL PINS; IRRADIATION; PHENIX REACTOR; REACTOR OPERATION; RUPTURES; SODIUM; SWELLING; TRANSIENT OVERPOWER ACCIDENTS
- Descriptors DEC
- ACCIDENTS; ALKALI METALS; BREEDER REACTORS; DEFORMATION; ELEMENTS; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; FAILURES; FAST REACTORS; FBR TYPE REACTORS; FUEL ELEMENTS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; METALS; OPERATION; PELLETS; PLUTONIUM REACTORS; POOL TYPE REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SODIUM COOLED REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Available as DVD-ROM Data in PDF format. Folder Name: FullPaper; Paper ID: ICONE23-2040.pdf; 7 refs., 23 figs., 3 tabs.