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Title: DETERMINATION OF BURNUP OF FAST REACTOR FUELS.

Authors:
; ;
Publication Date:
Research Org.:
Argonne National Lab., Ill.
OSTI Identifier:
4731424
Report Number(s):
ANL-7575
NSA Number:
NSA-24-001996
Resource Type:
Technical Report
Resource Relation:
Other Information: UNCL. Orig. Receipt Date: 31-DEC-70
Country of Publication:
United States
Language:
English
Subject:
N38150* -Power Reactor Development-Fuels; BURNUP; EFFICIENCY; FAST REACTORS; FISSION PRODUCTS; FUELS; MONITORING; PERFORMANCE; RARE EARTHS; URANIUM DIOXIDE; REACTORS, FAST/fuel burnup in, methods for measuring; FISSION PRODUCTS/content in fast reactor fuels of rare earth, use for burnup calculations of; URANIUM OXIDES UO$sub 2$/burnup in fast fuels of, comparison of methods for measuring

Citation Formats

Larsen, R.P., Meyer, R.J., and Crouthamel, C.E. DETERMINATION OF BURNUP OF FAST REACTOR FUELS.. United States: N. p., 1970. Web. doi:10.2172/4731424.
Larsen, R.P., Meyer, R.J., & Crouthamel, C.E. DETERMINATION OF BURNUP OF FAST REACTOR FUELS.. United States. doi:10.2172/4731424.
Larsen, R.P., Meyer, R.J., and Crouthamel, C.E. Sat . "DETERMINATION OF BURNUP OF FAST REACTOR FUELS.". United States. doi:10.2172/4731424. https://www.osti.gov/servlets/purl/4731424.
@article{osti_4731424,
title = {DETERMINATION OF BURNUP OF FAST REACTOR FUELS.},
author = {Larsen, R.P. and Meyer, R.J. and Crouthamel, C.E.},
abstractNote = {},
doi = {10.2172/4731424},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1970},
month = {10}
}