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Title: Calculation of the composition of reactor-irradiated 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 13ncm 2 sec were assumed. Calculation methods, assumptions concerning cross sections, and possible methods of producing specific nuclides are discussed.

Authors:
 [1];  [1]
  1. 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):
IDO-16571
NSA Number:
NSA-14-011048
DOE Contract Number:  
AT(10-1)-205
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-60
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 reactor-irradiated heavy nuclides. United States: N. p., 1959. Web. doi:10.2172/4178593.
Schuman, R. P., & Tromp, R. L. Calculation of the composition of reactor-irradiated heavy nuclides. United States. doi:10.2172/4178593.
Schuman, R. P., and Tromp, R. L. Thu . "Calculation of the composition of reactor-irradiated heavy nuclides". United States. doi:10.2172/4178593. https://www.osti.gov/servlets/purl/4178593.
@article{osti_4178593,
title = {Calculation of the composition of reactor-irradiated 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},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1959},
month = {12}
}