Analysis of Spent Fuel Assay with a Lead Slowing Down Spectrometer

Conference · Sun Sep 06 00:00:00 EDT 2009

OSTI ID:1039305

Gavron, Victor I. ^[1]; Smith, L. Eric ^[2]; Ressler, Jennifer J. ^[2]

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1. Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
2. Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)

Assay of fissile materials in spent fuel that are produced or depleted during the operation of a reactor, is of paramount importance to nuclear materials accounting, verification of the reactor operation history, as well as for criticality considerations for storage. In order to prevent future proliferation following the spread of nuclear energy, we must develop accurate methods to assay large quantities of nuclear fuels. We analyze the potential of using a Lead Slowing Down Spectrometer for assaying spent fuel. We conclude that it is possible to design a system that will provide around 1% statistical precision in the determination of the ²³⁹Pu, ²⁴¹Pu and ²³⁵U concentrations in a PWR spent-fuel assembly, for intermediate-to-high burnup levels, using commercial neutron sources, and a system of ²³⁸U threshold fission detectors. Pending further analysis of systematic errors, it is possible that missing pins can be detected, as can asymmetry in the fuel bundle.

• Research Organization: Los Alamos National Laboratory (LANL), Los Alamos, NM (United States); Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: AC52-06NA25396
• OSTI ID: 1039305
• Report Number(s): LA-UR-10-07334; LA-UR-10-7334; TRN: US1202144
• Resource Relation: Conference: GLOBAL 2009 , Paris (France), 6 Sep 2009
• Country of Publication: United States
• Language: English

Related Subjects

07 ISOTOPES AND RADIATION SOURCES
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ACCURACY
ASYMMETRY
BURNUP
CRITICALITY
DESIGN
FISSILE MATERIALS
FISSION
FUEL ELEMENT CLUSTERS
NEUTRON SOURCES
NUCLEAR ENERGY
NUCLEAR FUELS
PROLIFERATION
REACTOR OPERATION
SLOWING-DOWN
SPECTROMETERS
SPENT FUELS
STORAGE
VERIFICATION
Nuclear Criticality Safety Program (NCSP)
Spent Fuel
Fissile Materials Assay