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Title: INVESTIGATIONS OF NEUTRON CHARACTERISTICS FOR SALT BLANKET MODELS; INTEGRAL FISSION CROSS SECTION MEASUREMENTS OF NEPTUNIUM, PLUTONIUM, AMERICIUM AND CURIUM ISOTOPES

Abstract

No abstract prepared.

Authors:
; ;
Publication Date:
Research Org.:
Los Alamos National Lab., NM (US)
Sponsoring Org.:
US Department of Energy (US)
OSTI Identifier:
786708
Report Number(s):
LA-UR-01-5345
TRN: US0111287
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 Sep 2001
Country of Publication:
United States
Language:
English
Subject:
73 NUCLEAR PHYSICS AND RADIATION PHYSICS; AMERICIUM ISOTOPES; CROSS SECTIONS; CURIUM ISOTOPES; FISSION; NEPTUNIUM ISOTOPES; NEUTRONS; PLUTONIUM ISOTOPES; MATHEMATICAL MODELS

Citation Formats

E. FOMUSHKIN, G. NOVOSELOV, and ET AL. INVESTIGATIONS OF NEUTRON CHARACTERISTICS FOR SALT BLANKET MODELS; INTEGRAL FISSION CROSS SECTION MEASUREMENTS OF NEPTUNIUM, PLUTONIUM, AMERICIUM AND CURIUM ISOTOPES. United States: N. p., 2001. Web.
E. FOMUSHKIN, G. NOVOSELOV, & ET AL. INVESTIGATIONS OF NEUTRON CHARACTERISTICS FOR SALT BLANKET MODELS; INTEGRAL FISSION CROSS SECTION MEASUREMENTS OF NEPTUNIUM, PLUTONIUM, AMERICIUM AND CURIUM ISOTOPES. United States.
E. FOMUSHKIN, G. NOVOSELOV, and ET AL. 2001. "INVESTIGATIONS OF NEUTRON CHARACTERISTICS FOR SALT BLANKET MODELS; INTEGRAL FISSION CROSS SECTION MEASUREMENTS OF NEPTUNIUM, PLUTONIUM, AMERICIUM AND CURIUM ISOTOPES". United States. doi:. https://www.osti.gov/servlets/purl/786708.
@article{osti_786708,
title = {INVESTIGATIONS OF NEUTRON CHARACTERISTICS FOR SALT BLANKET MODELS; INTEGRAL FISSION CROSS SECTION MEASUREMENTS OF NEPTUNIUM, PLUTONIUM, AMERICIUM AND CURIUM ISOTOPES},
author = {E. FOMUSHKIN and G. NOVOSELOV and ET AL},
abstractNote = {No abstract prepared.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = 2001,
month = 9
}

Conference:
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  • Neutron characteristics of salt blanket micromodels containing eutectic mixtures of sodium, zirconium and uranium sulphides were measured on FKBN-2M, BIGR and MAKET installations. The effective fission cross sections of neptunium, plutonium, americium and curium isotopes were measured on the neutron spectra formed by micromodels. KEYWORDS: transmutation, minor actinides, fluoride salts, micromodel, critical assembly, neutron spectrum, multiplication coefficient, fission, effective cross section, nuclear track detector, nuclear data library
  • The following thermal-neutron fission cross sections have been measured in the thermal column of the Materials "Testing Reactor at Idaho Falls, Idaho: Pu/ sup 238/, 18.4 plus or minus 0.9 b; Am/sup 241/, 3.13 plus or minus 0.15 b; Am/sup 245/, 6390 plus or minus 500 b; Am/sup 243/, <0.072 b Cm/sup 243/, 690 plus or minus 50 b; Cm/sup 245/, 1880 plus or minus 150 b. In addition, a pile neutron capture cross section of 520 plus or minus 40 b has been measured for Pu/sup 238/. (auth)
  • A procedure, called the threshold cross section method was applied to our experimental data involving four uranium (/sup 233/U /sup 234/U, /sup 236/U, and /sup 238/U) and five plutonium (/sup 239/Pu, /sup 240/Pu, /sup 241/Pu, /sup 242/Pu, and /sup 244/Pu) isotopes to determine ratios of fission cross sections relative to /sup 235/U. The data were gathered using ionization fission chambers and the time-of-flight technique at the LLL 100-MeV electron linear accelerator: measurements span the neutron energy range of 0.001 to 30 MeV. Experimental uncertainties common to past measurements were either eliminated or significantly reduced in this study by use ofmore » the threshold method, thereby making higher accuracies possible. The cross section ratios are absolute in the sense that they do not depend on the work of others. Results from our ratios involving /sup 233/U, /sup 235/U, /sup 238/U, and /sup 239/Pu are used to illustrate this method.« less
  • The error information from the recent measurements of the fission cross section ratios of nine isotopes, /sup 230/Th, /sup 232/Th, /sup 233/U, /sup 234/U, /sup 236/U, /sup 238/U, /sup 237/Np, /sup 239/Pu, and /sup 242/Pu, relative to /sup 235/U at 14.74 MeV neutron energy was used to calculate their correlations. The remaining 36 non-trivial and non-reciprocal cross section ratios and their errors were determined and compared to evaluated (ENDF/B-V) values. There are serious differences but it was concluded that the reduction of three of the evaluated cross sections would remove most of them. The cross sections to be reduced aremore » /sup 230/Th - 13%, /sup 237/Np - 9.6% and /sup 239/Pu - 7.6%. 5 refs., 6 tabs.« less
  • Activation studies and U-233 production rate distribution measurements were carried out in a thorium oxide blanket assembly driven by a (d,t) neutron source. The experimental results are compared with the detailed neutronic calculations made by using Monte Carlo code MCNP and BMCCS2 cross section library, to check the validity of the cross section data.