Experiment on Iodine Transmutation Through High (original) (raw)
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Experiment on iodine transmutation by laser Compton scattering gamma ray
Journal of Physics: Conference Series, 2008
We carry out a research on nuclear transmutation through high energy gamma ray, to identify a way to reduce the hazards of long-lifetime radioactivity of nuclear waste. A laser Compton scattering gamma-ray facility was built on a storage ring at NewSUBARU and 17 MeV gamma-ray photons were produced. An investigation on the reaction rate of radioactive Iodine waste was carried out. Based on the characteristics of laser Compton scattering gamma rays, a cylindrical target was adopted for the irradiation experiment. The radioactivity of the irradiated target was measured and the transmutation reaction rate was deduced.
Experiment on gamma-ray generation and application
Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 2004
An experimental setup of gamma-ray generation through laser Compton scattering has been built on the NewSUBARU storage ring. The aim is to study nuclear transmutation, which is regarded as the first stage to explore the feasibility of developing a nuclear waste disposal system based on the concept of irradiating long-lived fission products by laser Compton scattering gamma ray. In this paper, the gamma-ray generation facility is presented, and some experimental results such as gamma-ray energy spectrum, intensity distribution, and the coupling efficiency of nuclear transmutation, are given. The experimental data is in good agreement with the analytic calculation or simulation analysis.
Energy Conversion and Management, 2008
We have proposed an approach to use a gamma ray for nuclear transmutation by Compton scattering of laser photons with high current accelerator. We had demonstrated laser Compton scatter to obtained 20MeV gamma ray to address transmutation rates with the giant resonance of Au and 129 Iodine.. Experiments for measurements of neutron spectrum and pair production positron and electron were performed for energy balance of this scheme and for target conditions. The results showed reaction rate was about 2~4% for appropriate photon energies and neutron energy was up to 4MeV in the calculation.
Journal of Nuclear Science and Technology, 2016
We have proposed a new selective isotope transmutation method using photonuclear reactions with quasi-monochromatic γ-ray beams. This method is based on the fact that the particle threshold of a long-lived fission product (LLFP) such as 93 Zr, 107 Pd, or 79 Se is lower than those of stable isotopes of the same chemical element. Therefore, this method has the excellent advantage that LLFPs cannot, in principle, be produced newly even if the target materials include stable isotopes in addition to LLFPs. Furthermore, this method is effective for 126 Sn, 135, 137 Cs, 90 Sr, and 3 H. The nuclear data involved and suitable γ-ray sources are discussed. Laser Compton scattering γ-ray sources and neutron capture γ-rays in nuclear reactors are candidates for this method.
Nuclear Science and Technology
An investigation on the nuclear transmutation of elemental long-lived fission product (LLFP) in a fast reactor is being conducted focusing on the I-129 LLFP (half-life 15.7 million years) to reduce the environmental burden. The LLFP assembly is loaded into the radial blanket region of a Japanese MONJU class sodium-cooled fast reactor (710 MWth, 148 days/cycle). The iodine element containing I-129 LLFP (without isotope separation) is mixed with YD2 and/or YH2 moderator material to enhance the nuclear transmutation rate. We studied the optimal moderator volume fraction to maximize the transmutation rate (TR, %/year) and the support factor (SF is defined as the ratio of transmuted to produced LLFP). We also investigated the effect of LLFP assembly loading position in the radial blanket and the severe power peak appeared at the fuel assembly adjacent to the LLFP assembly.
Laser transmutation of iodine-129
Applied Physics B: Lasers and Optics, 2003
We report the first successful laser-induced transmutation of 129 I, one of the key radionuclides in the nuclear fuel cycle. 129 I with a half-life of 15.7 million years is transmuted into 128 I with a half-life of 25 min through a (γ , n) reaction using laser-generated Bremsstrahlung. The integral cross-section value for the (γ , n) reaction is determined. These experiments offer a new approach to studying transmutation reactions with neutral and charged particles without resource to nuclear reactors or particle accelerators.
Applied Radiation and Isotopes, 1995
A deep geological repository for safe long-term storage of long-lived radioactive materials (waste) arising from nuclear fuel irradiation in reactors is a need generally accepted, whatever the strategy envisaged for further use of the irradiated fuel (e.g. : reprocessing and re-use of uranium and plutonium ; no reprocessing and final disposal).
Pramana, 2007
Target-blanket facility 'Energy + Transmutation' was irradiated by proton beam extracted from the Nuclotron Accelerator in Laboratory of High Energies of Joint Institute for Nuclear Research in Dubna, Russia. Neutrons generated by the spallation reactions of 0.7, 1.0, 1.5 and 2 GeV protons and lead target interact with subcritical uranium blanket. In the neutron field outside the blanket, radioactive iodine, neptunium, plutonium and americium samples were irradiated and transmutation reaction yields (residual nuclei production yields) have been determined using γ-spectroscopy. Neutron field's energy distribution has also been studied using a set of threshold detectors. Results of transmutation studies of 129 I, 237 Np, 238 Pu, 239 Pu and 241 Am are presented.
Transmutation of high-level nuclear waste by means of accelerator driven system
Wiley Interdisciplinary Reviews: Energy and Environment, 2013
To be able to answer the worlds' increasing demand for energy, nuclear energy must be part of the energy basket. The generation of nuclear energy produces, besides energy, also high-level nuclear waste, which is nowadays for geological storage. Transmutation of the minor actinides and long-lived fission products that arise from the reprocessing of the nuclear waste can reduce the radiological impact of these radioactive elements. Transmutation can be completed in an efficient way in fast neutron spectrum facilities. Both critical fast reactors and subcritical accelerator driven systems are potential candidates as dedicated transmutation systems. Nevertheless, an accelerator driven system operates in a flexible and safer manner even with a core loading containing a high amount of minor actinides leading to a high more-efficient transmutation approach.