Calculation of the composition of reactorirradiated heavy nuclides
Abstract
Calculations were made of the compositions of reactorIrradiated Th ^{230}. Th ^{232}, U ^{233}, U ^{235}, U ^{236}, U ^{238}, Pu ^{239}, Pu ^{242}, and Cm ^{244}. Pile fluxes with resonance flux per 1n E interval equal to 1/12 (typical of MTR fuel) or 1/30 (typical of MTR beryllium pieces) of the thermal flux were used for the calculations; thermal fluxes of 5 x 10 ^{13}, 2 x 10 ^{14}, and 1 x 10 ^{13n}cm ^{2} sec were assumed. Calculation methods, assumptions concerning cross sections, and possible methods of producing specific nuclides are discussed.
 Authors:

 Phillips Petroleum Co., Idaho Falls, ID (United States)
 Publication Date:
 Research Org.:
 Phillips Petroleum Co., Idaho Falls, ID (United States). Atomic Energy Division
 Sponsoring Org.:
 USDOE
 OSTI Identifier:
 4178593
 Report Number(s):
 IDO16571
 NSA Number:
 NSA14011048
 DOE Contract Number:
 AT(101)205
 Resource Type:
 Technical Report
 Resource Relation:
 Other Information: Orig. Receipt Date: 31DEC60
 Country of Publication:
 United States
 Language:
 English
 Subject:
 73 NUCLEAR PHYSICS AND RADIATION PHYSICS; BERYLLIUM; CROSS SECTIONS; CURIUM 244; ENERGY; FUELS; IRRADIATION; MTR; NEUTRON FLUX; NUCLEI; NUMERICALS; PLUTONIUM 239; PLUTONIUM 242; PRODUCTION; REACTORS; RESONANCE; THERMAL NEUTRONS; THORIUM 230; THORIUM 232; URANIUM 233; URANIUM 235; URANIUM 236; URANIUM 238
Citation Formats
Schuman, R. P., and Tromp, R. L. Calculation of the composition of reactorirradiated heavy nuclides. United States: N. p., 1959.
Web. doi:10.2172/4178593.
Schuman, R. P., & Tromp, R. L. Calculation of the composition of reactorirradiated heavy nuclides. United States. https://doi.org/10.2172/4178593
Schuman, R. P., and Tromp, R. L. Thu .
"Calculation of the composition of reactorirradiated heavy nuclides". United States. https://doi.org/10.2172/4178593. https://www.osti.gov/servlets/purl/4178593.
@article{osti_4178593,
title = {Calculation of the composition of reactorirradiated heavy nuclides},
author = {Schuman, R. P. and Tromp, R. L.},
abstractNote = {Calculations were made of the compositions of reactorIrradiated Th230. Th232, U233, U235, U236, U238, Pu239, Pu242, and Cm244. Pile fluxes with resonance flux per 1n E interval equal to 1/12 (typical of MTR fuel) or 1/30 (typical of MTR beryllium pieces) of the thermal flux were used for the calculations; thermal fluxes of 5 x 1013, 2 x 1014, and 1 x 1013ncm2 sec were assumed. Calculation methods, assumptions concerning cross sections, and possible methods of producing specific nuclides are discussed.},
doi = {10.2172/4178593},
url = {https://www.osti.gov/biblio/4178593},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1959},
month = {12}
}
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