[en] Anaerobic digestion of mixed leaf (MLW) and food wastes (FW) was used to explore the potential use of MLW as an accelerator for FW digestion in two parts for biogas production and as a waste management option in a university community. The effects of the single substrate of FW, co-digestion, ratio of MLW and FW (3:2 and 2:3) and ratio of waste feed to inoculum: F/I (0.1 and 0.4), and feeding frequency (every other day and every 2 days) were evaluated in two neutralized anaerobic reactors. The results showed that different mixture ratios with the same F/I ratio were the major factor on biogas (39.87 m³/kg VS_added) and CH₄ yield (25.99 m³/kg VS_added), including %COD removal (84.50%). Co-digestion had the same effect as F/I on biogas production. Only FW provided the lowest biogas and CH₄ yield. The use of a MLW:FW 2:3, F/I 0.4 mixture with every 2 days feeding provided higher biogas production and %COD removal than with every other day feeding. Two neutralized anaerobic reactors were suitable for digestion with a high F/I, and a wider interval feeding. This finding affirms the possibility of biogas production using MLW as the co-substrate with FW, as opposed to using FW alone.

[en] Neutron irradiation of CuO in nuclear reactors could result in Cu, Ni and Co radioisotopes. Radiochemical separation of these products could result in a pure radioactive source. In the present work, CuO powder was irradiated inside the 5 MW Tehran Research Reactor. After a cooling time, the irradiated powder dissolved using 0.5 M H₂SO₄ acid. Then sodium thiocyanate was used to participate copper. Then ⁶⁰Co was collected from the effluent and its volume was decreased to a desired value by heating of the liquid sample-involving glass

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No abstract available

[en] The alloying effects on X-ray fluorescence (XRF) parameters such as K shell fluorescence cross-sections (σ_kalpha, σ_Kbeta, σ_K), K shell average fluorescence yields (ω_K) and K to L shell vacancy transfer probabilities (η_KL) of V, Ti, Fe, Co and Ni 3 d transition metals in Permendur 49 (Fe₄₉Co₄₉V₂), Kovar (Fe₅₄Ni₂₉Co₁₇) and Ti₅₀Co₅₀ alloys have been carried out by X-ray fluorescence studies. K X-ray intensity ratios of these 3 d transition metals in both pure form and present alloys have been measured following excitation by 22.69 keV X-rays from a 10 m Ci ¹⁰⁹Cd radioactive point source. The characteristic K-X-ray spectra from samples were detected by a high-resolution Si (Li) solid-state detector. The investigated fluorescence parameters of present 3 d transition elements in alloys indicate significant differences with respect to the pure metals. Consequently, the observed change of the investigated fluorescence parameters can be attributed to the delocalization and charge transfer phenomena between the 3 d elements in alloys

[en] This paper reports the Co (α,αxn); x=1-3 reactions up to 120 MeV

[en] The authors used an activated sludge process to treat radioactive organic liquid waste. Organic liquid waste is difficult to treat by conventional radioactive liquid treatment processes, but in order to reduce long-term irradiation of the public the removal of radionuclides from such waste is preferable to dilution. Activated sludge processes are widely used for the biological treatment of sewage and are considered appropriate means for treating radioactive organic liquid waste. In this process, the fate of radionuclides eluted by treated water or immobilized by activated sludge, is extremely important for public safety and for the treatment of radioactive organic liquid waste. The authors performed uptake and desorption behavior experiments on the three short half-life radionuclides ¹³⁴Cs, ⁵⁷Co and ⁸⁵Sr, and used three nutritive types of artificial sewage as the feed solution. On the basis of the results, they discuss the uptake-desorption behavior of these radionuclides in an activated sludge process. The authors conclude that treatment of radioactive organic liquid waste by an activated sludge process is possible, but improvements must be made in the process if it is to be more effective

[en] Purpose: Radiotherapy plays a major role in the treatment strategy of childhood sarcomas. Consequences of treatment are likely to affect the survivor's quality of life significantly. We investigated the feasibility of spot-scanning proton therapy (PT) for soft tissue tumors in childhood. Methods and Materials: Sixteen children with soft tissue sarcomas were included. Median age at PT was 3.3 years. In 10 children the tumor histology was embryonal rhabdomyosarcoma. All tumors were located in the head or neck, parameningeal, or paraspinal, or pelvic region. In the majority of children, the tumor was initially unresectable (Intergroup Rhabdomyosarcoma Study [IRS] Group III in 75%). In 50% of children the tumors exceeded 5 cm. Fourteen children had chemotherapy before and during PT. Median total dose of radiotherapy was 50 cobalt Gray equivalent (CGE). All 16 children were treated with spot-scanning proton therapy at the Paul Scherrer Institute, and in 3 children the PT was intensity-modulated (IMPT). Results: After median follow-up of 1.5 years, local control was achieved in 12 children. Four children failed locally, 1 at the border of the radiation field and 3 within the field. All 4 children died of tumor recurrence. All 4 showed unfavorable characteristic either of site or histopathology of the tumor. Acute toxicity was low, with Grade 3 or 4 side effects according to Radiation Therapy Oncology Group/European Organization for Research and Treatment of Cancer (RTOG/EORTC) criteria occurring in the bone marrow only. Conclusions: Proton therapy was feasible and well tolerated. Early local control rates are comparable to those being achieved after conventional radiotherapy. For investigations on late effect, longer follow-up is needed

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[en] Dosimetry cross sections of ⁵⁹Co and ¹⁹⁷Au were evaluated based on the nuclear model calculation from threshold to 50 MeV for the application in accelerator based high energy neutron filed provided by ESNIT at JAERI, etc. For the ⁵⁹Co, the (n,2n), (n,3n), (n,4n), (n,p), (n,α) and (n,2nα) cross sections were evaluated and compared with available experimental data. The helium accumulation dosimetry cross section was also evaluated. For the ¹⁹⁷Au, the (n,2n), (n,3n), (n,4n) and helium production cross section were evaluated. Weak activation cross sections, (n,p) and (n,α), were also evaluated. (author)