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Title: ORIGEN-S (. cap alpha. ,n) neutron source spectra in borosilicate glass containing HLW (high-level waste)

Abstract

There is growing interest in the methodology and computational software for evaluating the (..cap alpha..,n) source spectra produced in mixtures of high-level waste (HLW) and borosilicate glass. The need for this development has been seen in previous work involving the analysis of HLW in borosilicate glass. Descriptions and applications of the ORIGEN-S method of computing neutron source spectra by both (..cap alpha..,n) reactions and spontaneous fission of UO/sub 2/ spent fuel have been reported previously. This summary presents a significant expansion of the ORIGEN-S (..cap alpha..,n) model to include ..cap alpha..-interactions with the light elements of borosilicate glass.

Authors:
; ;
Publication Date:
Research Org.:
Oak Ridge National Lab., TN (USA); Battelle Memorial Inst., Columbus, OH (USA). Office of Nuclear Waste Isolation
OSTI Identifier:
6529704
Report Number(s):
CONF-870601-11
ON: DE87005692
DOE Contract Number:
AC05-84OR21400
Resource Type:
Conference
Resource Relation:
Conference: Annual meeting of the American Nuclear Society, Dallas, TX, USA, 7 Jun 1987; Other Information: Microfiche only, copy does not permit paper copy reproduction
Country of Publication:
United States
Language:
English
Subject:
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; 73 NUCLEAR PHYSICS AND RADIATION PHYSICS; BOROSILICATE GLASS; ALPHA REACTIONS; HIGH-LEVEL RADIOACTIVE WASTES; WASTE FORMS; ALPHA DECAY; NEUTRONS; BARYONS; CHARGED-PARTICLE REACTIONS; DECAY; ELEMENTARY PARTICLES; FERMIONS; GLASS; HADRONS; MATERIALS; NUCLEAR REACTIONS; NUCLEONS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; WASTES; 052000* - Nuclear Fuels- Waste Management; 651000 - Nuclear Physics

Citation Formats

Hermann, O.W., Parks, C.V., and Ludwig, S.B.. ORIGEN-S (. cap alpha. ,n) neutron source spectra in borosilicate glass containing HLW (high-level waste). United States: N. p., 1987. Web.
Hermann, O.W., Parks, C.V., & Ludwig, S.B.. ORIGEN-S (. cap alpha. ,n) neutron source spectra in borosilicate glass containing HLW (high-level waste). United States.
Hermann, O.W., Parks, C.V., and Ludwig, S.B.. Thu . "ORIGEN-S (. cap alpha. ,n) neutron source spectra in borosilicate glass containing HLW (high-level waste)". United States. doi:. https://www.osti.gov/servlets/purl/6529704.
@article{osti_6529704,
title = {ORIGEN-S (. cap alpha. ,n) neutron source spectra in borosilicate glass containing HLW (high-level waste)},
author = {Hermann, O.W. and Parks, C.V. and Ludwig, S.B.},
abstractNote = {There is growing interest in the methodology and computational software for evaluating the (..cap alpha..,n) source spectra produced in mixtures of high-level waste (HLW) and borosilicate glass. The need for this development has been seen in previous work involving the analysis of HLW in borosilicate glass. Descriptions and applications of the ORIGEN-S method of computing neutron source spectra by both (..cap alpha..,n) reactions and spontaneous fission of UO/sub 2/ spent fuel have been reported previously. This summary presents a significant expansion of the ORIGEN-S (..cap alpha..,n) model to include ..cap alpha..-interactions with the light elements of borosilicate glass.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Jan 01 00:00:00 EST 1987},
month = {Thu Jan 01 00:00:00 EST 1987}
}

Conference:
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  • There is growing interest in the methodology and computational software for evaluating the (..cap alpha..,n) source spectra produced in mixtures of high-level waste (HLW) and borosilicate glass. The need for this development has been seen in previous work involving the analysis of HLW in borosilicate glass. Descriptions and applications of the ORIGEN-S method of computing neutron source spectra by both (..cap alpha..,n) reactions and spontaneous fission of UO/sub 2/ spent fuel have been reported previously. This summary presents a significant expansion of the ORIGEN-S (..cap alpha..,n) model to include alpha interactions with the light elements of borosilicate glass. The Battelle/Officemore » of Nuclear Waste Isolation requested this model extension. There is an associated interest in the use of Oak Ridge National Lab. shielding codes for analyzing HLW systems.« less
  • At the Savannah River Plant, the reference process for the immobilization of defense high-level waste (DHLW) for geologic storage is vitrification into borosilicate glass. During geologic storage for 10/sup 6/ y, the glass would be exposed to approx. 3 x 10/sup 10/ rad of ..beta.. radiation, approx. 10/sup 10/ rad of ..gamma.. radiation, and 10/sup 18/ particles/g glass for both ..cap alpha.. and ..cap alpha..-recoil radiation. This paper discusses tests of the effect of these radiations on the leachability and density of the glass. Even though the doses were large, no effect of the radiations was detected that reduced themore » effectiveness of the glass for long-term storage of DHLW even at doses corresponding to 10/sup 6/ years storage for the actual glass. For the tests, glass containing simulated DHLW was prepared from frit of the reference composition. Three methods were used to irradiate the glass: external irradiations with beams of approx. 200 keV Xe or Pb ions, internal irradiations with Cm-244 doped glass, and external irradiations with Co-60 ..gamma.. rays. Results with both Xe and Pb ions indicate that a dose of 3 x 10/sup 13/ ions/cm/sup 2/ (simulating > 10/sup 6/ years storage) does not significantly increase the leachability of the glass in deionized water. Tests with Cm-244 doped glass show no increase in leach rate in water or brine up to a dose of 10/sup 18/ ..cap alpha.. and ..cap alpha..-recoils/g glass. Results of larger doses are being examined. The density of the Cm-244 doped glass has decreased by 1% at a dose of 10/sup 18/ particles/g glass. With ..gamma..-radiation, the density has changed by < 0.05% at a dose of 8.5 x 10/sup 10/ rad. Results of leach tests in deionized water and brine indicated that this very large dose of ..gamma..-radiation increased the leach rate by only 20%. Also, the leach rates are lower in brine.« less
  • The major part of the neutron source in vitrified high-level waste is produced from the actinide {alpha}-particle emission interacting with the light elements in borosilicate glass. Models applying thick target ({alpha},n) yield data have been developed for the ALPHN code and ORIGEN-S at the Oak Ridge National Laboratory. The method requires the relation between the ({alpha},n) yields and the stopping powers of elements, which are constituents in a mixture, and the total ({alpha},n) yield of the mixture. An example is given of results computed by ALPHN, listing the calculated ({alpha},n) sources for each {alpha}-particle emitter in addition to the total.more » An example computed by ORIGEN-S is given, showing both the total ({alpha},n) spectrum and the total neutron spectrum, including spontaneous fission. A discussion of the limited validation work is also provided.« less
  • The major part of the neutron source in vitrified high-level waste is produced from the actinide {alpha}-particle emission interacting with the light elements in borosilicate glass. Models applying thick target ({alpha},n) yield data have been developed for the ALPHN code and ORIGEN-S at the Oak Ridge National Laboratory. The method requires the relation between the ({alpha},n) yields and the stopping powers of elements, which are constituents in a mixture, and the total ({alpha},n) yield of the mixture. An example is given of results computed by ALPHN, listing the calculated ({alpha},n) sources for each {alpha}-particle emitter in addition to the total.more » An example computed by ORIGEN-S is given, showing both the total ({alpha},n) spectrum and the total neutron spectrum, including spontaneous fission. A discussion of the limited validation work is also provided.« less