Zobrazeno 1 - 10
of 57
pro vyhledávání: '"S.R. Bierman"'
Autor:
R.J. Talbert, S.R. Bierman
To establish criticality safety margins utilizing burnup credit in the storage and transport of spent reactor fuels requires a knowledge of the uncertainty in the calculated fuel composition used in making the reactivity assessment. To provide data f
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f98137c315c886a38ed1fc1211dc3965
https://doi.org/10.2172/10193492
https://doi.org/10.2172/10193492
Autor:
S.R. Bierman, E.D. Clayton
Publikováno v:
Nuclear Technology. 54:131-144
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b2814029a64e48330581a7c79499d82f
https://doi.org/10.13182/nt81-a32730
https://doi.org/10.13182/nt81-a32730
Autor:
S.R. Bierman, E.D. Clayton
Publikováno v:
Nuclear Technology. 52:342-346
Fuel element storage racks in shipping casks or fuel basin storage pools are generally designed and built such that either structural materials and/or fixed neutron poisons create neutron flux traps between the fuel elements. To provide data for comp
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::677e126da1cbdce7e5de76900248bc34
https://doi.org/10.13182/nt81-a32708
https://doi.org/10.13182/nt81-a32708
Publikováno v:
Nuclear Technology. 49:40-46
Criticality benchmark-type data are obtained on four undermoderated FTR (Fast Test Reactor) fuel pin-water lattices with concrete reflection. The experiments were designed to serve as benchmarks for validating computer codes and nuclear data used in
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::4ef96de779ac3d1d8d4d85986625804d
https://doi.org/10.13182/nt80-a32504
https://doi.org/10.13182/nt80-a32504
Publikováno v:
Nuclear Science and Engineering. 78:121-125
A series of experiments was performed to determine the effect of gadolinium as a soluble neutron absorber on the criticality of fuel rod assemblies in uranyl nitrate solution. The gadolinium in the...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::86e2e42caf99391516d33e35661820c5
https://doi.org/10.13182/nse81-a20098
https://doi.org/10.13182/nse81-a20098
Autor:
E.D. Clayton, S.R. Bierman
Publikováno v:
Nuclear Science and Engineering. 61:370-376
The results from a series of criticality experiments with three different mixtures of oxides of plutonium and uranium are presented. The fuel mixtures consisted of /sup 235/U-depleted uranium homogenized with approximately 8, 15, and 30 wt percent pl
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3517a03638b40bd8dc8cb04eb3bbb004
https://doi.org/10.13182/nse76-a26923
https://doi.org/10.13182/nse76-a26923
Publikováno v:
Nuclear Science and Engineering. 55:51-57
Results are presented from a series of criticality experiments with homogeneous plutonium-uranium fuel mixtures with plutonium content in the range of 5 to 8 wt%. The H:(Pu+U) atomic ratios covered...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::867e85cf5fce70dd8c6070d39eb1ac4b
https://doi.org/10.13182/nse74-a23965
https://doi.org/10.13182/nse74-a23965
Publikováno v:
Nuclear Science and Engineering. 65:41-48
There is a continuing interest in the use of fixed neutron absorbers (poisons) for criticality control, since their use would permit safely handling larger quantities of nuclear materials with reduced probability of criticality. The effectiveness of
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::30ae22e2942be4636bd8b88a8456c36a
https://doi.org/10.13182/nse78-a27124
https://doi.org/10.13182/nse78-a27124
Publikováno v:
Nuclear Science and Engineering. 50:115-126
Data are presented from critical experiments with mixed PuO2-UO2 fuels containing 30.0, 14.62, and 7.89 wt% Pu and having H/X (H:Pu + U) atomic ratios of 47.4, 30.6, and 51.8, respectively. In addi...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::143fa5aa3bb7e40b232a6ef6ec33d47f
https://doi.org/10.13182/nse73-2
https://doi.org/10.13182/nse73-2