Zobrazeno 1 - 10
of 50
pro vyhledávání: '"R.R. Heinrich"'
The ACL activities covered IFR fuel reprocessing, corium-concrete interactions, environmental samples, wastes, WIPP support, Advanced Photon Source, H-Tc superconductors, EBWR vessel, soils, illegal drug detection, quality control, etc.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ee5594d1a9557455c84fb8b66b1725c6
https://doi.org/10.2172/10166234
https://doi.org/10.2172/10166234
The treatment of contaminated soil presents a significant technical problem. Soil-washing and chemical-extraction methods have proven to be effective for specific applications, but a process with more comprehensive treatment properties that is both c
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::841a43b1f9157fd0c41d0b32863108a0
https://doi.org/10.2172/7148507
https://doi.org/10.2172/7148507
The purpose of this report is to summarize the activities of the Analytical Chemistry Laboratory (ACL) at Argonne National Laboratory (ANL) for Fiscal Year 1991 (October 1990 through September 1991). This is the eighth annual report for the ACL. The
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::490b989b950d30e42b38b3c2f51f9b2c
https://doi.org/10.2172/5499461
https://doi.org/10.2172/5499461
Autor:
R.R. Heinrich, L.R. Greenwood
Publikováno v:
Journal of Nuclear Materials. :473-477
Thirty-one neutron cross sections have been extended to 44 MeV for dosimetry application at high energy accelerator sources. Integral testing in Be(d,n) fields at E d = 14, 16, and 40 MeV shows that 22 cross sections are accurate to within ± 10%. An
Publikováno v:
Nuclear Technology. 25:289-293
High flux level reaction rates are measured from the gamma-ray emission analysis of activated foils. These foils are analyzed nondestructively to eliminate error due to dissolution, dilution, and/o...
Development and Testing of Neutron Dosimetry Techniques for Accelerator-Based Irradiation Facilities
Publikováno v:
Nuclear Technology. 41:109-128
Integral tests have been made for 27 nuclear activation cross sections required for neutron dosimetry at accelerator-based irradiation facilities. Thirteen materials were irradiated in a well-defined geometry using neutrons produced by stopping 14- t
Publikováno v:
Journal of Nuclear Materials. :889-893
The radiation damage induced in nickel, niobium and 316SS by T (d,n) and Be (d,n) neutrons was evaluated by microstructural analysis and mechanical property measurements. Also, the neutron flux gradients in the Be (d,n) neutron source were compared t
Publikováno v:
Nuclear Science and Engineering. 54:263-272
Yields have been determined for the short-lived gamma-ray emitting nuclides 95Zr, 97Zr, 103Ru, 131I, and 140Ba, produced in fission of 235U and 239Pu by both thermal and fast neutrons and in fissio...
Publikováno v:
Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology. 15:200-203
The neutron capture cross sections of 236 U have been measured for monoenergetic neutrons in the energy range 0·30 to 1·7 MeV.
The Analytical Chemistry Laboratory is a full-cost-recovery service center, with the primary mission of providing a broad range of technical support services to the scientific and engineering programs at ANL. In addition, ACL conducts a research prog
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2b30bf827520c3cc2f37e75b4680a6b3
https://doi.org/10.2172/5955611
https://doi.org/10.2172/5955611