Published 1979
| Version v1
Book
Simulations of an unprotected loss-of-flow accident with a 37-pin bundle in the sodium loop safety facility
Creators
- 1. Argonne Natl Lab, IL
Description
Two experiments, each using an hexagonal array of 37 full-length mixed-oxide fuel pins, have simulated an unprotected loss-of-flow accident under prototypic sodium-cooled fast-reactor conditions. These two experiments are summarized and experimental results are compared with accident analysis calculations. It is shown that the voiding behavior predicted by the SAS3D accident analysis code closely agrees with the measurements but the rates of blockage formation and fuel melting are somewhat over estimated by the code. 8 refs
Additional details
Publishing Information
- Publisher
- ANS.
- Imprint Place
- LaGrange Park, IL
- Imprint Title
- Proceedings of the international meeting on fast reactor safety technology, 1979
- Journal Page Range
- p. 896-904.
Conference
- Title
- International meeting on fast reactor safety technology.
- Dates
- 19 - 23 Aug 1979.
- Place
- Seattle, WA, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 12627146
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FUEL PINS; LMFBR TYPE REACTORS; LOSS OF FLOW; SIMULATION
- Descriptors DEC
- ACCIDENTS; BREEDER REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUEL ELEMENTS; LIQUID METAL COOLED REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS