Analysis of internal fuel motion during PINEX-2 experiment

Conference · Fri Sep 01 00:00:00 EDT 1978

OSTI ID:6266837

Padilla, A Jr; Baars, R E; Porten, D R; Randklev, E H

This paper describes the analyses performed for the PINEX-2 experiment to calculate the ejection of molten fuel into the reflector and fission gas plenum for an internally-vented fuel pin during a simulated 5$/s transient overpower excursion. The LAFM code was used to predict the transient fuel melting and fission gas release, and the HOTPIM and FUMO-T codes were used to predict the fuel ejection. The analytical results were compared with initial data from both the Pinhole-TV Imaging System and the fast-neutron hodoscope, as well as post-transient examinations of the fuel pin.

• Research Organization: Hanford Engineering Development Lab., Richland, WA (USA)
• DOE Contract Number: EY-76-C-14-2170
• OSTI ID: 6266837
• Report Number(s): HEDL-SA-1658-S; CONF-790310-6; TRN: 79-015727
• Resource Relation: Conference: Specialists workshop on predictive analysis of material dynamics in LMFBR safety expts, Los Alamos, NM, USA, 13 Mar 1979
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FUEL ELEMENT FAILURE
HYDRAULICS
LMFBR TYPE REACTORS
FUEL PINS
TRANSIENT OVERPOWER ACCIDENTS
FUEL CANS
MELTDOWN
PRESSURE GRADIENTS
ACCIDENTS
BREEDER REACTORS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
FUEL ELEMENTS
LIQUID METAL COOLED REACTORS
MECHANICS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding