Research Article |
Corresponding author: Valery V. Korobeynikov ( korob@ippe.ru ) Academic editor: Georgy Tikhomirov
© 2023 Valery V. Korobeynikov, Valery V. Kolesov, Igor A. Ignatiev.
This is an open access article distributed under the terms of the Creative Commons Attribution License (CC BY 4.0), which permits unrestricted use, distribution, and reproduction in any medium, provided the original author and source are credited.
Citation:
Korobeynikov VV, Kolesov VV, Ignatiev IA (2023) Computational simulation of minor actinide burning in a BN-600 reactor with fuel without uranium and plutonium. Nuclear Energy and Technology 9(1): 59-64. https://doi.org/10.3897/nucet.9.102776
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The paper presents the results of studies on the burning of minor actinides (MA) extracted from SNF of thermal reactors in a BN-600 reactor, which uses the complete set of MAs instead of traditional nuclear fuel types: uranium and/or plutonium. The advantages of such approach to MA burning are that long-lived waste is recycled and energy is produced that can be used, e.g., to generate electricity. Besides, where, e.g., a reactor with uranium or MOX fuel is used for transmutation, apart from burning “foreign” minor actinides, it will additionally generate “its own” MAs. The studies have shown that such reactor can be efficient only if based on fast neutrons, which is due to the specific properties of the minor actinide neutron capture and fission cross-sections as compared with traditional fuel nuclides. The calculation results have shown rather a high rate of MA transmutation and burning in a reactor fueled with minor actinides.
transmutation, minor actinides, Am, Np, Cm, burning of minor actinides, fast neutron nuclear reactor, neutron spectrum, plutonium, nuclear fuel, SNF, SNF storage, biological hazard, radiotoxicity
Disposal of radioactive waste in nuclear power is becoming a growinglysensitiveissue as spent nuclear fuel builds up, the nuclear reactor fleet is enlarged, and NPP units are decommissioned after their design life expires. Specifically challenging in addressing this issue are minor actinides (MA). Two major options are discussed by research community for disposal of nuclear waste, including direct disposal of SNF (an open fuel cycle) with all radioactive elements built up or in the process of build-up, and recycling of long-lived high-level MAs by irradiation in the reactor. The process of transmutation is defined as conversion of MAs and their daughter nuclides to stable or short-lived fission products (
An important peculiarity of the approach proposed for the MA burning is the fact that MAs as such represent the required source of neutrons, unlike conventional methods when the major sources of neutrons are fuel nuclides such as uranium and plutonium. The efficiency of MA burning in the proposed approach is much higher than offered by conventional approaches.
Note that this paper does not discuss any issues involved in the practical implementation of and the arrangement of operations in such facility. A number of additional studies are required to justify in detail the conceptual approach described. Studies are primarily required for justifying the safety and functionality of FAs with MA fuel.
MAs are isotopes of americium, curium and neptunium formed as the result of the reactor operation and affecting significantly the SNF and RW handling methods.This is explained by the fact that, despite being produced in small quantities in reactors, MAs contribute greatly to the SNF decay heat power and radiotoxicity in a longer term. Table
Nuclide | T 1/2, years | Decay heat power, | Critical mass |
---|---|---|---|
W/kg | kg | ||
U-233 | 1,59E+05 | 2,81E-01 | 1,56E+01 |
U-235 | 7,04E+08 | 6,00E-05 | 4,65E+01 |
Np-237 | 2,14E+06 | 2,10E-02 | 5,89E+01 |
Pu-238 | 8,77E+01 | 5,60E+02 | 9,76E+00 |
Pu-239 | 2,41E+04 | 2,00E+00 | 9,96E+00 |
Pu-240 | 6,56E+03 | 7,00E+00 | 3,70E+01 |
Pu-241 | 1,43E+01 | 6,40E+00 | 1,28E+01 |
Pu-242 | 3,75E+05 | 1,20E-01 | 8,71E+01 |
Am-241 | 4,33E+02 | 1,15E+02 | 6,18E+01 |
Am-242m | 1,41E+02 | 4,50E+00 | 1,26E+01 |
Am-243 | 7,37E+03 | 6,40E+00 | 1,83E+02 |
Cm-242 | 162,8 сут | 1,21E+05 | 1,32E+01 |
Cm-243 | 2,91E+01 | 1,86E+03 | 6,14E+00 |
Cm-244 | 1,81E+01 | 2,80E+03 | 2,51E+01 |
Cm-245 | 8,50E+03 | 5,70E+00 | 1,26E+01 |
Cm-246 | 4,76E+03 | 1,00E+01 | 8,33E+01 |
An analysis into the dependence of the capture and fission cross-sections on energy for the nuclides, MAs are composed of, shows (
Since the Am-241 and Np-237 fission cross-sections are higher than the capture cross-sections only in the “fast” region of energies, and these nuclides account for the most part of the MAs, the reactor with MA fuel can be only a fast neutron reactor. This paper considers the possibility for the entire set of minor actinides in the unloaded SNF to be used as fuel, without isolation of americium, neptunium and curium.
Therefore, fast neutron reactors, the fuel in which consists of only minor actinides with no traditional uranium and/or plutonium, will be capable to burn efficiently the MAs accumulated in SNF of thermal neutron reactors.
It is important that most of the MAs in such reactor will be converted to fragments in the process of fission. Another major argument in favor of a reactor with MA fuel is that MA burning does not only eliminate the accumulation of new actinides but also enablesgeneration of electricity. The complication of a traditional nuclear reactor based on uranium or MOX fuel also by the MA burning issue worsens economics and its technical parameters. It is therefore expected that it will be more advantageous to use dedicated reactors the key mission of which is efficient MA burning. Such reactors are naturally expected to be more expensive than traditional reactors. However, they are expected to be capable to burn sufficiently large amounts of MAs, so such dedicated reactors will be few in the nuclear power system.
The results of the studies into the possibility for using Am-241 and Np-237 (
The Table
Isotope | Mass fraction in SNF | Initial composition for calculations, metallic fue, 1024 1/cm3 | Initial composition for calculations, oxide fuel, 1024 1/cm3 |
---|---|---|---|
Np-237 | 4,95Е–1 | 2,5704Е–2 | 1,1555Е–2 |
Am-241 | 3,16Е–1 | 1,0786Е–2 | 8,14Е–3 |
Am-242m | 1,03Е–3 | 3,501Е–5 | 2,63335Е–5 |
Am-243 | 1,48Е–1 | 5,01Е–3 | 3,7846Е–3 |
Cm-242 | 4,13Е–9 | 1,39Е–10 | 1,089Е–10 |
Cm-243 | 4,36Е–4 | 1,4587Е–5 | 1,14546Е–5 |
Cm-244 | 3,69Е–2 | 1,22938Е–3 | 9,6592Е–4 |
Cm-245 | 2,62Е–3 | 8,694Е–5 | 6,8335Е–5 |
Cm-246 | 4,77Е–4 | 1,576444Е–5 | 1,23963Е–5 |
Cm-247 | 1,01Е–5 | 3,324163Е–7 | 2,61535Е–7 |
O-16 | – | 4,91186E–2 |
Table
Nuclide | Oxide, kg | Metal, kg |
---|---|---|
Np-237 | 2,82E+02 | 5,89E+01 |
Am-241 | 1,20E+02 | 6,18E+01 |
Am-242m | 1,58E+01 | 1,26E+01 |
Am-243 | 4,85E+02 | 1,83E+02 |
Cm-242 | 1,84E+01 | 1,32E+01 |
Cm-243 | 7,91E+00 | 6,14E+00 |
Cm-244 | 3,73E+01 | 2,51E+01 |
Cm-245 | 1,47E+01 | 1,26E+01 |
Cm-246 | 1,42E+02 | 8,33E+01 |
Cm-247 | 1,08E+01 | 8,91E+00 |
«Вектор» МА | 1,93E+02 | 6,15E+01 |
This section presents the results of computational studies to investigate the efficiency of MA transmutation in a BN-600 reactor model (
Figs
Everything in this model that is beyond the core, both axially and radially, is homogenized. The heterogeneous structure has been preserved only for the FAs and the fuel elements within the fuel column. The FA cross-section is shown in Fig.
As fuel, instead of uranium and plutonium, the computational model used the MA composition shown in Table
The computational studies were undertaken for two MA fuel options: in the form of metal and in the form of oxide. SERPENT, a Monte Carlo code, was used for the studies (
The Keff value at the irradiation start time grows initially and then drops. This phenomenon is explained by the isotopes produced which prove to be more efficient in terms of contribution to the multiplication factor than the original ones.
Figs
Fig.
The change in the mass of Cm nuclides depending on the operating time of a nuclear reactor with MA fuel can be traced in Figs
A question remains what will isolation of Am from the MA composition give? It will be all the same required afterwards to burn Am separately, and Cm will accumulate again! The solution is to isolate MA from SNF rapidly, before Pu-241, the major source for the Am formation, decays.The faster SNF is processed, the less Am will be contained in MAs.
Neutronic computational studies have been undertaken with respect to burning of minor actinides in a reactor with fuel without uranium and plutonium. Burning of the complete composition of MAs (Am, Np, Cm) isolated from SNF has been investigated.
An important argument in favor of a reactor with minor actinide fuel is that MA burning does not only eliminate the accumulation of new actinides but will also enable generation of electricity. The complication of a nuclear reactor based on uranium or MOX also by the MA burning issue worsens economics and its technical parameters. It is therefore expected that it will be more advantageous to use dedicated reactors the key mission of which will be efficient recycling of MAs. They can be naturally more expensive than traditional ones. It is however expected that it will be possible to burn rather large quantities of MAs in such reactors, so such dedicated reactors will be few in the nuclear power system.
The computational studies were performed using two BN-600 reactor models. One of the models used metallic MA fuel, and the other used oxide MA fuel. It has been shown that MA burning is fairly efficient in both models and with different fuel.
The computational studies have shown that the decay heat from the “complete” set from VVER SNF exceeds that from the same mass of “pure” americium by just 20%.
A major reduction in the mass of Cm nuclides with a high decay power can be achieved by burning MAs with a low Am content. Practical implementation of such approach requires small SNF cooling times prior to the MA isolation since the source of Am-241 is short-lived Pu-241.
The problem of developing a real design of a reactor with fuel based only on minor actinides has not so far been resolved.