| 1. |
- Edwards, Lyndon, et al.
(författare)
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Worldwide activities
- 2017
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Ingår i: Molten Salt Reactors and Thorium Energy. ; , s. 635-774
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Bokkapitel (övrigt vetenskapligt/konstnärligt)
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| 2. |
- Gudowski, Waclaw, et al.
(författare)
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Review of the European project - Impact of Accelerator-Based Technologies on Nuclear Fission Safety (IABAT)
- 2001
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Ingår i: Progress in nuclear energy (New series). - 0149-1970 .- 1878-4224. ; 38:1-2, s. 135-151
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Tidskriftsartikel (refereegranskat)abstract
- The IABAT project - Impact of Accelerator Based Technologies on Nuclear Fission Safety - started in 1996 in the frame of 4(th) Framework Programme of the European Union, R&D specific programme Nuclear fission safety 1994-1998, area A.2 Exploring innovative approaches/Fuel cycle concepts, as one of the first common European activities in ADS. The project was completed October 31, 1999. The overall objective of the IABAT project has been a preliminary assessment of the potential of Accelerator-Driven Systems (ADS) for transmutation of nuclear waste and for nuclear energy production with minimum waste generation. Moreover, more specific topics related to nuclear data and code development for ADS have been studied in more detail. Four ADSs have been studied for different fuel/coolant combinations: liquid metal coolant and solid fuel, liquid metal coolant and dispersed fuel, and fast and thermal molten salt systems. Target studies comprised multiple target solutions and radiation damage problems in a target environment. In a tool development part of the project a methodology of subcriticality monitoring has been developed based on Feynman-alpha and Rossi-alpha methods. Moreover, a new Monte-Carlo burnup code taking full advantage of continuous neutron cross-section data has been developed and benchmarked. Impact on the risk from high-level waste repositories fi om radiotoxicity reduction using ADS has been assessed giving no crystal-clear benefits of ADS for repository radiotoxicity reduction but concluding some important prerequisites for effective transmutation. In proliferation studies important differences between critical reactors and ADS have been underlined and non-proliferation measures have been proposed. In assessment of accelerator technology costing models have been created that allow the circular and linear accelerator options to be compared and the effect of parameter variations examined. The calculations reported show that cyclotron systems would be more economical, due mainly to the advantage of the cost of RF power supplies. However, the accelerator community regards with skepticism the possibility of transporting and extracting more than a 10mA beam current from a 1GeV cyclotron and therefore technical factors may limit the application of cyclotrons. Finally, this review summarizes development of nuclear data in the energy region between 20 Mev and 150 MeV. Neutron and proton transport data files for Fe, Ni, Pb, Th, U-238 and Pu-239 have been created. The high-energy part of the data files consists completely of results from model calculations, which are benchmarked against the available experimental data. Although there is obviously future work left regarding fine-tuning of several parts of the data files, the representation of nuclear reaction information up to 150 MeV is already better than can be attained with intranuclear cascade codes.
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| 3. |
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| 4. |
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| 5. |
- Arzhanov, Vasily, et al.
(författare)
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Diagnostics of core barrel vibrations by in-core and ex-core neutron noise
- 2003
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Ingår i: Progress in nuclear energy (New series). - 0149-1970 .- 1878-4224. ; 43:04-jan, s. 151-158
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Tidskriftsartikel (refereegranskat)abstract
- Diagnostics of core-barrel vibrations has-traditionally been made by use of ex-vessel neutron detector signals. We suggest that in Addition to the ex-core noise, also the in-core noise, induced by core barrel vibrations, be also used. This would enhance the possibilities of diagnostics where the number of the ex-core detectors is not sufficient or their positions are disadvantageous for effective diagnostics, especially for shell-mode vibrations. To this order, the theory of in-core noise induced by a fluctuating core boundary has been elaborated and applied to the diagnostics of beam and shell mode vibrations. The formulas were tested on some measurements taken in the Ringhals PWRs. The results confirm the validity of the model itself, and the possibilities for enhanced diagnostics were demonstrated. A more effective use of these novel possibilities requires more in-core detectors and/or better detector positioning.
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| 6. |
- Arzhanov, Vasily, et al.
(författare)
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Localization of a vibrating control rod pin in pressurized water reactors using the neutron flux and current noise
- 2000
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Ingår i: Nuclear Technology. - 0029-5450 .- 1943-7471. ; 131:2, s. 239-251
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Tidskriftsartikel (refereegranskat)abstract
- It has been proposed that the fluctuations of the neutron current called the current noise, can be used in addition to the scalar noise in reactor diagnostic problems. The possibility of the localization of a vibrating control rod pin in a pressurized water reactor control assembly is investigated by using the scalar neutron noise and the two-dimensional radial current noise as measured at one central point in the assembly. Art explicit localization technique is elaborated in which the searched position is determined as the absolute minimum of a minimization function. The technique is investigated in numerical simulations. The results of the simulation tests show the potential applicability of the method.
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| 7. |
- Pazsit, I., et al.
(författare)
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Linear reactor kinetics and neutron noise in systems with fluctuating boundaries
- 2000
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Ingår i: Annals of Nuclear Energy. - 0306-4549 .- 1873-2100. ; 27:15, s. 1385-1398
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Tidskriftsartikel (refereegranskat)abstract
- The general theory of linear reactor kinetics and that of the induced neutron noise is developed for systems with varying size, i.e. in which the position of the boundary fluctuates around a stationary value. The point kinetic and adiabatic approximations are defined by a generalisation of the flux factorisation, and the full solution of the general problem with an arbitrarily fluctuating boundary is given by the Green's function technique. The correctness of the general solution is proven both generally and also by considering the simple case of a 2-D cylindrical reactor with a fluctuating radius, in which case a direct compact solution is possible.
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| 8. |
- Szieberth, M., et al.
(författare)
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EXPERIMENTAL DEMONSTRATION OF NEUTRON FLUCTUATION ANALYSIS BASED ON THE CONTINUOUS SIGNAL OF FISSION CHAMBERS: NEUTRON MULTIPLICITY AND REACTOR NOISE MEASUREMENTS
- 2021
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Ingår i: Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021. ; , s. 1752-1761
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Konferensbidrag (refereegranskat)abstract
- The paper presents experimental demonstration of the feasibility of a new neutron fluctuation analysis method which was developed based on L. Pál's stochastic model of the continuous signal of fission chambers. Results of multiplicity counting and reactor noise experiments performed with this new method are summarized and compared with measurement results obtained by traditional pulse counting methods. The first results are promising and further development of the methods is planned.
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