Nondestructive assay techniques for recycles $sup 233$U fuel for high- temperature gas-cooled reactors
Nondestructive fissile material assay techniques are reviewed for application to the refabrication of recycled $sup 233$U fuel for High Temperature Gas-Cooled Reactors (HTGR). The refabrication processes and fuel characteristics are identified and explained, and nondestructive assay techniques are evaluated in light of these characteristics and assay requirements. It is concluded that currently developed and implemented gamma-ray assay techniques for $sup 235$U and $sup 239$Pu are not applicable to $sup 233$U fuel because of its high radioactivity. Calorimetry has potential for $sup 233$U fuel assay if appropriate corrections for isotopic composition can be applied. For most nondestructive assay requirements, active interrogation methods must be employed. Neutron interrogation systems using either $sup 252$Cf or $sup 124$Sb-Be neutron sources and delayed or prompt fission neutron detection offer the greatest potential for assay of HTGR recycle $sup 233$U fuel. The presence of hydrogen in some of the fuel forms during processing and the particulate nature of the HTGR fuel complicate the direct application of these neutron interrogation techniques. Photofission techniques, which offer enhanced penetrability for the assay of bulk fuel quantities or fuel elements, cannot be evaluated for this application because of a lack of basic data. (auth)
- Research Organization:
- Oak Ridge National Lab., TN
- NSA Number:
- NSA-33-005108
- OSTI ID:
- 4139736
- Journal Information:
- Nucl. Mater. Manage., v. 4, no. 1, pp. 18-35, Other Information: Orig. Receipt Date: 30-JUN-76
- Country of Publication:
- United States
- Language:
- English
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