Zobrazeno 1 - 10
of 18
pro vyhledávání: '"RICHARD G. STRICKERT"'
Autor:
Yasuo Nishizawa, Takashi Kiguchi, Setsuo Kobayashi, Kenji Takumi, Michiro Yokomi, Ryohsuke Tsutsumi, Harukuni Tanaka, Siegfried Brandes, Günter Lohnert, Folkmar A. Schwarz, Heinz E. Tischer, Ronald N. Drake, William S. Rickman, Nadine D. Holder, James B. Strand, Warren F. Witzig, Serradell Vincente, C. S. MacDougall, C. K. Bayne, R. B. Roberson, Siegfried Malang, Klaus Rust, Milan Hrovat, Hans Huschka, Lothar Rachor, Günter Mühling, Heinz Zimmerman, Dhanpat Rai, Richard G. Strickert, Gary L. McVay, Yehuda Eyal, Aaron Kaufman, Yoshiaki Himeno, Kazuo Mukai, Tatsuro Iguchi, Ken Yamamoto, Fumio Nagai, Masao Fujita, Hubertus Nickel, Philip J. Ennis, Florian Schubert, Hans Schuster, Dieter Barschdorff, Dietmar Wetzlar, Yasunori Bessho, Hiroshi Motoda, Mitsutaka Watanabe
Publikováno v:
Nuclear Technology. 58:1-7
Publikováno v:
Inorganic and Nuclear Chemistry Letters. 16:551-555
Air-equilibrated suspensions of 238 Pu and 239 Pu compounds in dilute salt solutions produced HNO 3 at a rate which increased with the H + concentration.
Publikováno v:
ract. 33:201-206
Americium(III) hydroxide solubility was measured in dilute salt solutions under an argon atmosphere. The equilibrium, attained in < 23 days, was approached from both over and undersaturation. Thermodynamic equilibrium constants (K/sub S10//sup 0/) fo
Publikováno v:
Geochimica et Cosmochimica Acta. 45:2257-2265
Americium-241 concentrations in solutions contacting contaminated sediments for up to 2 yr were measured as a function of pH. Steady-state concentrations were reached within a few days. The solubility-limited Am concentration was found to decrease ap
Publikováno v:
Nuclear Technology. 58:69-76
To help predict concentrations of neptunium leached from nuclear waste repositories in geologic environments, the solubility of neptunium in a neptunium-doped borosilicate glass, which simulates a high-level waste glass, was investigated. The concent
Autor:
Richard G. Strickert, Dhanpat Rai
Publikováno v:
MRS Proceedings. 6
Knowledge of Pu solid phases present in nuclear wastes is important for predicting the geochemical behavior of Pu. Thermodynamic data and experimental measurements using discrete Pu compounds, Pu-doped borosilicate glasses (simulating a high-level wa
Publikováno v:
MRS Proceedings. 44
Experiments based on a modified MCC-3S test method were conducted to investigate the solubility of U(VI) hydroxide (the mineral schoepite) and Np(IV) hydrous oxide at ambient temperature. The solubility of U(VI) hydroxide was investigated in carbonat
Publikováno v:
MRS Proceedings. 44
At the request of the Basalt Waste Isolation Project, the Materials Characterization Center has collected and developed a set of procedures for a waste form compliance test method (MCC-14.4). The purpose of the test is to measure the steady-state con
A computer program (ARDISC, the Argonne Dispersion Code) is described which simulates the migration of nuclides in porous media and includes first order kinetic effects on the retention constants. The code allows for different absorption and desorpti
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::29d943f6d80409b6745097219834597b
https://doi.org/10.2172/6206257
https://doi.org/10.2172/6206257
Publikováno v:
ACS Symposium Series ISBN: 9780841208278
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c185b4961d3ecfe2989193660b350ae9
https://doi.org/10.1021/bk-1984-0246.ch008
https://doi.org/10.1021/bk-1984-0246.ch008