Measurement of the Relative /Sup 235/U Concentration and the Absolute /Sup 235/U Content of Individual HTGR Fuel Particles

doi 10.2172/7149706
Full Text
Abstract

Available in full text

Date
Authors
Publisher

Office of Scientific and Technical Information (OSTI)

Related search

Improved Material Accounting for Plutonium Processing Facilities and a /Sup 235/U-HTGR Fuel Fabrication Facility

1975English

Neutron Inelastic-Scattering Cross Sections of /Sup 232/Th, /Sup 233/U, /Sup 235/U, /Sup 238/U, /Sup 239/Pu and /Sup 240/Pu. [LMFBR]

1982English

Calculation of Resonance Self Shielding in $Sup 235$U

1973English

A MULTILEVEL ANALYSIS OF THE $Sup 235$U FISSION CROSS SECTION.

1968English

Neutron Methods for Measuring {Sup 235}U Content in UF{sub 6} Gas

1996English

Measurement of the Neutron-Induced Fission Cross-Section of /Sup 243/Am Relative to /Sup 235/U From 0. 1 MeV to 30 MeV

1977English

FEASIBILITY OF Pu$sup 239$-U$sup 235$-Fueled CORES TO PREDICT Pu$sup 239$- FUELED CORE DIMENSIONS

1962English

Neutron Multiplicity for Neutron Induced Fission of /Sup 235/U, /Sup 238/U, and /Sup 239/Pu as a Function of Neutron Energy

1986English

An ESTIMATE OF THE NONLEAKAGE PROBABILITY FOR BARE AQUEOUS HOMOGENEOUS U$sup 235$ REACTORS

1957English

Amanote Research

Note-taking for researchers

Follow Amanote

© 2025 Amaplex Software S.P.R.L. All rights reserved.

Privacy PolicyRefund Policy