Characterization of an Advanced Gadolinium Neutron Absorber Alloy by Means of Neutron Transmission

Conference · Sun Sep 09 00:00:00 EDT 2007

OSTI ID:918177

Wachs, G. W. ^[1]; Sterbentz, J. W. ^[1]; Montierth, L. M. ^[1]; Tovesson, F. K. ^[2]; Hill, T. S. ^[2]

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1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
2. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

Neutron transmission experiments were performed on samples of an advanced nickel-chromium-molybdenum-gadolinium (Ni-Cr-Mo-Gd) neutron absorber alloy. The primary purpose of the experiments was to demonstrate the thermal neutron absorbing capability of the alloy at specific gadolinium dopant levels. The new alloy is to be deployed for criticality control of highly enriched DOE SNF. For the transmission experiments, alloy test samples were fabricated with 0.0, 1.58 and 2.1 wt% natural gadolinium dispersed in a Ni-Cr-Mo base alloy. The transmission experiments were successfully carried out at the Los Alamos Neutron Science Center (LANSCE). Measured data from the neutron transmission experiments were compared to calculated results derived from a simple exponential transmission formula using only radiative capture cross sections. Excellent agreement between the measured and calculated results demonstrated the expected strong thermal absorption capability of the gadolinium poison and in addition, verified the measured elemental composition of the alloy test samples. The good agreement also indirectly confirmed that the gadolinium was dispersed fairly uniformly in the alloy and the ENDF VII radiative capture cross section data were accurate.

• Research Organization: Idaho National Lab. (INL), Idaho Falls, ID (United States); Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); USDOE Assistant Secretary for Environment Management (EM); National Spent Nuclear Fuel Program; USDOE Idaho Operations Office (IO)
• DOE Contract Number: AC07-99ID-13727
• OSTI ID: 918177
• Report Number(s): INL/CON-07-12838; TRN: US0805255
• Resource Relation: Conference: ANS Global 2007: Advanced Nuclear Fuel Cycles and Systems, Boise, ID (United States), 9-13 Sep 2007; Related Information: https://www.ans.org/meetings/view-14/
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ABSORPTION
ALLOYS
CAPTURE
CRITICALITY
CROSS SECTIONS
GADOLINIUM
LOS ALAMOS
NEUTRON ABSORBERS
NEUTRONS
NUCLEAR FUELS
THERMAL NEUTRONS
Nuclear Criticality Safety Program (NCSP)
Spent Nuclear Fuel (SNF)
Evaluated Nuclear Data File (ENDF)
Thermal Neutron Absorber
Neutron Transmission Experiments
Macroscopic Cross Sections
Standardized Canister