Fuel motion induced by a sharp burst TUCOP: PFR/TREAT test L07

Conference · Tue Jan 01 00:00:00 EST 1985

OSTI ID:5633068

Robinson, W R; Doerner, R C; Morman, J A; Bauer, T H; Herbert, R

In the transient-undercooling-driven overpower (TUCOP) accident scenario for moderate-to-high-sodium-void-worth-LMFBR cores, some computer codes predict large reactivity increases caused by compactive in-pin fuel motion in low power subassemblies during a power burst resulting from sodium voiding in the lead fuel subassemblies. In this hypothetical scenario, the low power subassemblies are predicted to experience midplane failure with relatively cold cladding, which inhibits radial dispersal and results in a momentary accumulation of fuel around the midplane failure site. A major objective of PFR/TREAT Test L07 was to simulate such low-power-subassembly TUCOP conditions, measure the associated fuel motion and evaluate the fuel-motion predictions.

• Research Organization: Argonne National Lab., IL (USA); UKAEA Atomic Energy Establishment, Winfrith
• DOE Contract Number: W-31-109-ENG-38
• OSTI ID: 5633068
• Report Number(s): CONF-850610-7; ON: DE85006121
• Resource Relation: Conference: Annual meeting of the American Nuclear Society, Boston, MA, USA, 9 Jun 1985
• 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
LMFBR TYPE REACTORS
TRANSIENT OVERPOWER ACCIDENTS
THERMAL STRESSES
COMPUTER CALCULATIONS
FUEL PINS
LIQUID FLOW
REACTOR SAFETY
ACCIDENTS
BREEDER REACTORS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID FLOW
FUEL ELEMENTS
LIQUID METAL COOLED REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SAFETY
STRESSES
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding