Preliminary report on the Pinex at TREAT. [Pinhole experiment for nonredundant pinhole array imaging of LMFBR fuel pins]

Conference · Thu Jan 01 00:00:00 EST 1976

OSTI ID:7334837

Berzins, G J; Han, K S; Roach, W H

The neutron image of a GETR fuel pin was observed in a pinhole experiment (Pinex) performed at TREAT. The signal amplitude, recorded with intensified television cameras, compared well with expectations. The results carry favorable implications for continued development of nonredundant pinhole array techniques, as well as for refinement of single pinhole experiments, as diagnostic tools for the LMFBR safety program.

• Research Organization: Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 7334837
• Report Number(s): LA-UR-76-2238; CONF-761022-5; TRN: 77-005700
• Resource Relation: Conference: Fuel and clad motion diagnostics for LMFBR safety test facilities conference, Chicago, IL, USA, 9 Oct 1976
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LMFBR TYPE REACTORS
MELTDOWN
TEST FACILITIES
TREAT REACTOR
REMOTE VIEWING EQUIPMENT
APERTURES
FUEL ELEMENT FAILURE
FUEL PINS
GETR REACTOR
NEUTRON RADIOGRAPHY
NONDESTRUCTIVE ANALYSIS
REACTOR EXPERIMENTAL FACILITIES
REACTOR SAFETY
ACCIDENTS
AIR COOLED REACTORS
BREEDER REACTORS
CHEMICAL ANALYSIS
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL ELEMENTS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HOMOGENEOUS REACTORS
INDUSTRIAL RADIOGRAPHY
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
LIQUID METAL COOLED REACTORS
MATERIALS TESTING
NONDESTRUCTIVE TESTING
OPENINGS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SOLID HOMOGENEOUS REACTORS
TANK TYPE REACTORS
TEST REACTORS
TESTING
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding
220000 - Nuclear Reactor Technology