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Nuclear transmutation
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Lecture Physical science: Chapter 3 provide students with content about: radioactivity; the strong nuclear force; half-life and transmutation; radiometric dating; nuclear fission; mass–energy equivalence; nuclear fusion;... Please refer to the detailed lecture content!
41p
diepkhinhchau
18-09-2023
5
4
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The ADS (accelerator driven system) is recognized as a promising system to annihilate the radioactivity of nuclear waste with its inherent safety feature and waste transmutation potential. Thus, conceptual designs of ADS are widely carrying out.
10p
visnape
30-01-2023
7
4
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The VVER-1000 reactors are nowadays widespread used in Russia and numerous countries. With almost 3000 MW of thermal, VVER-1000 is a candidate to transmute minor actinides (MAs) which are the main contributors to the radiotoxicity and decay heat of nuclear spent fuel (SNF).
11p
visnape
30-01-2023
8
4
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The paper presents calculation results of conceptual design for a 10-MWt highflux multi-purpose research reactor of a Research Centre for Nuclear Energy Science and Technology (RCNEST) of Viet Nam.
19p
vidumbledore
06-01-2023
18
4
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This reactor is modeled for depletion calculations. The behavior of special fuel elements that mirror fuel composition as envisioned for large scale transmutation facilities, namely inert-matrix fuels with an increased minor actinide content, are investigated within this reactor environment.
10p
vironald
15-12-2022
11
4
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Americium is a strong contributor to the long term radiotoxicity of high activity nuclear waste. Transmutation by irradiation in nuclear reactors of long-lived nuclides like 241Am is therefore an option for the reduction of radiotoxicity and heat production of waste packages to be stored in a repository.
11p
vironald
15-12-2022
11
3
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The performance of the fusion–fission hybrid system based on the molten salt (flibe) blanket, driven by a plasma based fusion device, was analyzed by comparing transmutation scenarios of actinides extracted from the LWR (Sweden) and RBMK (Lithuania) spent nuclear fuel in the scope of the EURATOM project BRILLIANT.
9p
vironald
15-12-2022
10
3
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The METAPHIX programme is a collaboration between the Central Research Institute of Electric Power Industry (CRIEPI, Japan) and the Joint Research Centre - Institute for Transuranium Elements (JRC-ITU) of the European Commission dedicated to investigate the safety and effectiveness of a closed nuclear fuel cycle based on Minor Actinides (MA: Np, Am, Cm) separation from spent fuel, incorporation in metal alloy fuel and transmutation in fast reactor.
8p
vironald
15-12-2022
15
3
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"The journal of Nuclear science and technology - Volume 9/Number 4, 2019" present bubble behavior in liquid-gas two-phase flow behind a cross-shaped obstacle in a vertical circular duct; study on transmutation efficiency of the VVER-1000 fuel assembly with different minor actinide compositions; determination of in situ detection efficiency for IM-NAA of non-standard geometrical samples...
60p
trinhthamhodang1218
14-03-2021
16
2
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"The journal of Nuclear science and technology - Volume 9/Number 3, 2019" present nuclear transmutation of long-lived fission product i-129 in radial blanket of sodium-cooled fast reactor; calculation results for enhancing ability of I-131 radioisotope production using tellurium dioxide target on the dalat nuclear research reactor; temporal variation of stable isotopic values for dissolved nitrogen compounds in paddy water environment...
59p
trinhthamhodang1218
14-03-2021
12
1
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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.
8p
trinhthamhodang1218
14-03-2021
10
2
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The design and testing of an irradiation rig using flux screen method for NTD-Si at the DNRR are necessary to have a better understanding and experience in NTD-Si application. The new irradiation rig using various screen materials (stainless steel, aluminum and light water) was designed, installed and tested in the core of DNRR.
8p
trinhthamhodang1218
14-03-2021
9
1
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In this work, we report studies on a fast low power accelerator driven system model as a possible experimental facility, focusing on its capabilities in terms of measurement of relevant integral nuclear quantities.
8p
christabelhuynh
30-05-2020
12
1
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Partitioning and transmutation strategy R&D for nuclear spent fuel: the SACSESS and GENIORS projects
In this context, and in the continuity of the FP7 EURATOM SACSESS project, GENIORS focuses on the reprocessing of MOX fuel containing minor actinides, taking into account safety issues under normal and mal-operation.
8p
christabelhuynh
29-05-2020
10
1
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Today, nuclear power produces 11% of the world’s electricity. Nuclear power plants produce virtually no greenhouse gases or air pollutants during their operation. Emissions over their entire life cycle are very low.
8p
christabelhuynh
29-05-2020
7
1
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In this research, we investigated the burnup characteristics and the conversion of fertile 232Th into fissile 233U in the core of a Sodium-Cooled Fast Reactor (SFR). The SFR fuel assemblies were designed for burning 232Th fuel (fuel pin 1) and 233U fuel (fuel pin 2) and include mixed minor actinide compositions. Monte Carlo simulations were performed using Serpent Code1.1.19 to compare with CRAM (Chebyshev Rational Approximation Method) and TTA (Transmutation Trajectory Analysis) method in the burnup calculation mode.
6p
minhxaminhyeu5
30-06-2019
32
0
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In addition, damage caused by Ni two-step reactions was considered. Estimations were made for the annulus spacers in a CANDU reactor that are located axially along a fuel channel and made of Inconel X-750. The calculation results indicate that the transmutation gas production from the Ni two-step reactions is predominant as the effective full power year increases.
7p
minhxaminhyeu3
12-06-2019
6
0
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The burnup equation of nuclides is one of the most equations in nuclear reactor physics, which is generally coupled with transport calculations. The burnup equation describes the variation of the nuclides with time. Because of its very stiffness and the need for large time step, this equation is solved by special methods, for example transmutation trajectory analysis (TTA) or the matrix exponential methods where the matrix exponential is approximated by CRAM.
5p
minhxaminhyeu3
12-06-2019
7
0
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The aim of this paper is to determine neutronic performances of the light water reactor (LWR) spent fuel mixed with fertile thorium fuel in a FFHR. Time dependent three dimensional calculations for major technical data, such as blanket energy multiplication, tritium breeding ratio, cumulative fissile fuel enrichment and burnup have been performed by using Monte Carlo Neutron-Particle Transport code MCNP5 1.4, coupled with a novel interface code MCNPAS.
10p
minhxaminhyeu3
25-06-2019
19
0
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This book covers new experimental and theoretical studies that focus on the modern developments of nuclear fission, aiming at various applications in a wide range of fields and bringing together scientists working in different fields related to nuclear fission.
219p
namde04
03-05-2013
62
6
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