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DOE announces “monumental step” in SRS target recovery program
The Department of Energy has announced the successful transfer of the first Mark-18A target from the Savannah River Site to Savannah River National Laboratory, marking “the beginning of operations for a newly established radiochemical separation capability to recover valuable isotopes.” The agency stated that the Mark-18A Target Recovery Program—which involves the DOE National Nuclear Security Administration, the Office of Environmental Management, and the Office of Science—is demonstrating “how legacy materials previously destined for disposal can be recovered and transformed into valuable resources.”
Koichi Okuno, Masayoshi Kawai, Hitoshi Yamada
Nuclear Technology | Volume 168 | Number 2 | November 2009 | Pages 545-552
Shielding Materials | Special Issue on the 11th International Conference on Radiation Shielding and the 15th Topical Meeting of the Radiation Protection and Shielding Division (Part 2) / Radiation Protection | doi.org/10.13182/NT09-A9241
Articles are hosted by Taylor and Francis Online.
Neutron shielding is very important for neutron facility construction. Concrete is usually used for neutron shielding. Although concrete is inexpensive, massive thickness is required. In the present work, a novel neutron shielding concrete using colemanite rock and peridotite rock was developed. Its shielding performance was evaluated through the transmission experiments by using 252Cf spontaneous fission source and the calculations with the MCNP5 code. The results show that a neutron 1/100 attenuation length of the neutron concrete shield with a typical colemanite content of 10 wt% is shorter by a factor of 1.7 than that of normal concrete. The results show that the shielding performance becomes better when the thickness is still thicker and the incident neutron spectrum is softer.The colemanite-peridotite concrete (neutron shielding concrete) was applied to biological shields of the Versatile High Intensity Total Diffractometer on the Japan Proton Accelerator Research Complex. Using this concrete permitted a reduction in the thickness of the shielding wall by a maximum of 25 cm compared to the normal concrete and a reduction of the iron in the beam dump.