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Title: Segregation of fission products to surfaces of UO{sub 2}

Abstract

No abstract prepared.

Authors:
 [1]
  1. and others
Publication Date:
Research Org.:
Los Alamos National Lab., NM (US)
Sponsoring Org.:
US Department of Energy (US)
OSTI Identifier:
769009
Report Number(s):
LA-UR-00-5823
TRN: US0100738
DOE Contract Number:
W-7405-ENG-36
Resource Type:
Conference
Resource Relation:
Conference: Conference title not supplied, Conference location not supplied, Conference dates not supplied; Other Information: PBD: 1 Dec 2000
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 36 MATERIALS SCIENCE; FISSION PRODUCTS; SEGREGATION; URANINITES

Citation Formats

Stanek, C. Segregation of fission products to surfaces of UO{sub 2}. United States: N. p., 2000. Web.
Stanek, C. Segregation of fission products to surfaces of UO{sub 2}. United States.
Stanek, C. Fri . "Segregation of fission products to surfaces of UO{sub 2}". United States. doi:. https://www.osti.gov/servlets/purl/769009.
@article{osti_769009,
title = {Segregation of fission products to surfaces of UO{sub 2}},
author = {Stanek, C.},
abstractNote = {No abstract prepared.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Dec 01 00:00:00 EST 2000},
month = {Fri Dec 01 00:00:00 EST 2000}
}

Conference:
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  • The current paper gives a summary of the mass spectrometric analysis of the irradiated and non-irradiated UO{sub 2} and ThO{sub 2} targets using a nuclear version ICP-MS in a glove-box. To compensate for nonspectroscopic interferences caused by a large excess of uranium and thorium compensate for nonspectroscopic interferences caused by a large excess or uranium and thorium in the matrix and to reduce sample size, and automatic flow-injection system (FI) and a high-performance liquid chromatography (HPLC) system enclosed in a glove box were connected to the ICP-MS. The operating condition and FI analyses parameter were optimized. As high uranium concentrationsmore » suppress strongly the signal of trace elements in an ICP-MS, the separation method was evaluated to elute uranium first. By the introduction of a post column valve, the uranium fraction was directly passed to the waste. In this way, the instrument was not exposed to high amounts of dissolved solid, and better detection limits could be reached. About 220 mg of the non-irradiated and irradiated highly radioactive samples were dissolved in ml 65% HNO{sub 3}, ThO{sub 2} in 65% HNO{sub 3}, with 1.5 mMol (NH{sub 4}){sub 2}SiF{sub 6}. Diluted solutions were analyzed for isotopes in the mass-range between 55-230 a.m.u. for U and 55-240 a.m.u. for Th. The concentrations of the spallation and fission products were determined semiquantitatively. The experimental results are in reasonable agreement with the predicted values from the theoretical calculations.« less
  • In our experiments, post-irradiation anneal of lightly-irradiated UO/sub 2/ was used to measure the release kinetics of the volatile fission products Xe, I, and Te. The fraction of a particular fission product retained in a specimen was measured by gamma-ray spectroscopy before and following an anneal.
  • The critical masses and fission and explosive energy releases of PuO/sub 2/, PuO/sub 2/-UO/sub 2/, UO/sub 2/ and UO/sub 3/ assemblies were calculated. The choice of parameters used in the model is conservative and was chosen after review of appropriate plants that have been and are proposed for construction in the future. The resulting data envelopes are intended to include any conceivable set of circumstances that could ultimately lead to a nuclear incident. All energy release analysis was performed for initial fission spikes only; recriticality mechanisms were not considered.