Burnup and radiation embrittlement of the U-Mo neutron source target
The burnup of uranium target plates of the NSC KIPT neutron source was studied. An analysis of experimental work on the effect of neutron irradiation on the strength and plastic properties of uranium and U-Mo alloys under conditions close to the operation of the target has been carried out. A descri...
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Національний науковий центр «Харківський фізико-технічний інститут» НАН України
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| Cite this: | Burnup and radiation embrittlement of the U-Mo neutron source target / B.V. Borts, V.V. Gann, A.Yu. Zelinsky, A.A. Parkhomenko, A.F. Vanzha, Yu.A. Marchenko, I.V. Patochkin // Problems of Atomic Science and Technology. — 2022. — № 2. — С. 57-61. — Бібліогр.: 31 назв. — англ. |
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| author | Borts, B.V. Gann, V.V. Zelinsky, A.Yu. Parkhomenko, A.A. Vanzha, A.F. Marchenko, Yu.A. Patochkin, I.V. |
| author_facet | Borts, B.V. Gann, V.V. Zelinsky, A.Yu. Parkhomenko, A.A. Vanzha, A.F. Marchenko, Yu.A. Patochkin, I.V. |
| citation_txt | Burnup and radiation embrittlement of the U-Mo neutron source target / B.V. Borts, V.V. Gann, A.Yu. Zelinsky, A.A. Parkhomenko, A.F. Vanzha, Yu.A. Marchenko, I.V. Patochkin // Problems of Atomic Science and Technology. — 2022. — № 2. — С. 57-61. — Бібліогр.: 31 назв. — англ. |
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| container_title | Вопросы атомной науки и техники |
| description | The burnup of uranium target plates of the NSC KIPT neutron source was studied. An analysis of experimental work on the effect of neutron irradiation on the strength and plastic properties of uranium and U-Mo alloys under conditions close to the operation of the target has been carried out. A description of the processes of radiation embrittlement is presented, taking into account the deformation and porosity of materials at various levels of burnup. An estimate of the expected service life of a uranium target under irradiation has been carried out.
Досліджено вигоряння уранових мішеней джерела нейтронів ННЦ ХФТІ. Проведено аналіз експериментальних робіт по впливу нейтронного опромінення на міцнісні та пластичні властивості урану і сплаву U-Mo в умовах, наближених до умов роботи мішені. Проведена оцінка очікуємого ресурсу роботи пластин уранової мішені під опроміненням.
Исследовано выгорание урановых мишеней источника нейтронов ННЦ ХФТИ. Проведен анализ экспериментальных работ по влиянию нейтронного облучения на прочностные и пластическиe свойства урана и сплава U-Mo в условиях, приближенных к условиям работы мишени. Проведена оценка ожидаемого ресурса работы пластин урановой мишени под облучением.
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ISSN 1562-6016. ВАНТ. 2022. №2(138) 57
https://doi.org/10.46813/2022-138-057
UDC 669.18.2
BURNUP AND RADIATION EMBRITTLEMENT
OF THE U-Mo NEUTRON SOURCE TARGET
B.V. Borts, V.V. Gann, A.Yu. Zelinsky, A.A. Parkhomenko, A.F. Vanzha,
Yu.A. Marchenko, I.V. Patochkin
National Science Center “Kharkov Institute of Physics and Technology”, Kharkiv, Ukraine
E-mail: borts@kipt.kharkov.ua
The burnup of uranium target plates of the NSC KIPT neutron source was studied. An analysis of experimental
work on the effect of neutron irradiation on the strength and plastic properties of uranium and U-Mo alloys under
conditions close to the operation of the target has been carried out. A description of the processes of radiation embrit-
tlement is presented, taking into account the deformation and porosity of materials at various levels of burnup. An
estimate of the expected service life of a uranium target under irradiation has been carried out.
INTRODUCTION
Recently, at the NSC KIPT, together with the Ar-
gonne National Laboratory of the USA, the physical
launch of the research nuclear installation “Neutron
source based on a subcritical assembly controlled by an
electron accelerator” was carried out as a stage in the cre-
ation of new generation nuclear power plants [1].
Two types of neutron producing targets (NPT) are be-
ing considered for use: depleted uranium (U-Mo) based
alloy and tungsten. Previously, an analysis was made of
nuclear-physical processes occurring in uranium and
tungsten targets under irradiation [2, 3]. It was found that
the greatest contribution to the rate of damage formation
in a tungsten target is made by the elastic interaction of
high-energy electrons with nuclei, and the maximum rate
of dose accumulation is about 0.83 dpa/year and is
achieved in the second plate of the tungsten target (at a
depth of ~ 1 cm). An analysis of the nuclear-physical pro-
cesses taking place in a uranium target under irradiation
has shown that the greatest contribution to the damage
rate is made by uranium photofission fragments, as a re-
sult of which the maximum defect creation rate will be
100 dpa/year.
The physical and mechanical properties, and hence
the service life of a uranium target, directly depend on the
level of uranium burnup, the value of which can have a
great effect on the structure, radiation growth, radiation
embrittlement, and other service characteristics of the tar-
get. Burnup, i.e. the relative change in the concentration
of uranium atoms due to fission processes will be
0.55 10-3 per year, which approximately corresponds to
the values in thermal reactors of the WWER type [2].
The purpose of this work was to conduct a compara-
tive analysis of the strength and plastic characteristics
(radiation embrittlement and hardening) of uranium and
U-(7…9%) Mo alloys, as the material of the target plates
of the NSC KIPT under different level of burnup.
Interest in the radiation resistance of these alloys is
also due to the fact that they are today one of the main
candidates for the material of monolithic nuclear fuel for
experimental and research reactors of a new generation
[4].
1. BURNUP OF THE URANIUM TARGET OF
A NEUTRON SOURCE
The studies of nuclear-physical processes occurring
in uranium and tungsten targets under electron irradiation
and leading to radiation defect formation and burnup are
also the subject of [2, 3] and earlier works on mathemat-
ical modeling. It was shown that, at a depth of about 1 cm
an electromagnetic shower develops in the target, which
causes photofission of U-238 nuclei, while the fission
fragments create a large number of radiation defects in
the uranium target. It was found that the highest level of
burnup is achieved at a depth of ~ 1.4 cm and is
5.5 10-2 % per year of continuous operation (Fig. 1). In
this case, the maximum rate of creation of radiation de-
fects in uranium reaches 100 dpa/year.
Fig. 1. Burnup rate U along the length of the neutron
source target; z – depth in cm
Uranium burnup is accompanied by the release of
solid and gaseous fission products and the production of
helium, while Xe and Kr dominate over other fission
products. The rate of their formation is very high, and is
about 0.2…0.3 atoms per fission. With an annual burnup
level of 5.5 10-2 %, the helium concentration in the ura-
nium target will be about 1500 appm. These processes
lead to the fact that gas nanobubbles with high internal
pressure can form in the uranium-molybdenum target
even at burnup of the order of one percent [5].
When analyzing the experimental work performed on
samples for mechanical testing irradiated in reactors, we
use the following ratios between the values a dose of
mailto:borts@kipt.kharkov.ua
58 ISSN 1562-6016. ВАНТ. 2022. №2(138)
1 dpa corresponds to: 1…2 10-4 % uranium burnup, and a
neutron fluency of about 21017 n/cm [2, 6, 7].
2. COMPARATIVE ANALYSIS OF DATA ON
RADIATION EMBRITTLEMENT AND
HARDENING OF URANIUM AND
URANIUM-MOLYBDENUM ALLO1YS
The results of analysis of the strain-to-fracture de-
pendence during tensile tests of natural uranium speci-
mens and U-(7…9%)Mo alloy specimens irradiated in re-
actors are shown in Fig. 2,a. As follows from the figure,
the value of deformation before destruction of all irradi-
ated samples lies below one percent.
The following regularities can be noted:
a) The greatest change in ductility to failure is ob-
served when samples from natural uranium and uranium-
molybdenum alloys burnup by less than 0.02%. At the
same time, their plasticity at room temperature decreases
from 11…19 to 0.4…0.5%, i.e. significant radiation em-
brittlement is observed.
b) Having a significant advantage over natural ura-
nium in a number of characteristics – structural stability,
resistance to swelling, recrystallization under irradiation
[15], uranium-molybdenum alloys exhibit practically the
same reduction in deformation before failure, as uranium
(difference in fractions of a percent).
The plates of the NPT KIPT uranium target will re-
ceive a maximum dose of about 100 dpa/year [2], and
have a burnup level of about 0.055% during the same
time (shown by the arrow in Fig. 2). This can lead to al-
most complete embrittlement of the target material, asso-
ciated with a high level of damage to the uranium alloy:
– in a single act of uranium fission, several hundred thou-
sand point radiation defects are formed.
Up to burnup levels of the order of 0.02% for any ma-
terials irradiated and tested at low temperature < 0.3 Tm
radiation hardening is observed – an increase in the yield
strength, while reducing the tensile strength of uranium
(shown by a double dashed line in Fig. 2,b).
A comparison of the results shown in Fig. 2 shows
that at burnup levels of more than 0.1%, the destruction
of natural uranium samples is accompanied by a signifi-
cant decrease in the ultimate strength, and also, as shown
in [7, 13, 16], a decrease in its density (by 5%). Fracture
occurs in the elastic region, without traces of plastic flow.
The dependence of the ultimate strength of polycrys-
talline uranium on the level of burnup is shown in
Fig. 2,b. Like the analogous dependence for the fracture
strain, it has a stage nature: the first stage of strength re-
duction occurs at burnup of less than 0.01%. Further, up
to burnup of approximately 0.1%, there is a small plateau,
followed by final radiation softening associated with
complete embrittlement of the material.
The dependence of the tensile strength on burnup for
the U-Mo alloy largely coincides with the same depend-
ence for natural uranium. This is especially pronounced
in the range of 0.01…0.1% – in the “plateau” section.
At a burnup level of about a percent, the tensile
strength decreased from 1050…1100 MPa to
250…399 MPa (see Fig. 2,b). Structural studies have
shown that the fracture occurred without any signs of
plasticity, at the elastic part of the stress-strain curve
[13, 14]. However, it should be noted that the data for this
alloy were obtained under bending deformation, which is
considered a “softer” type of test.
In the same works, it was found that at this level of
burnup, the value of the elastic modulus decreases signif-
icantly due to the presence of porosity, which was
3…5%. The development of porosity in uranium is stim-
ulated by the formation of gaseous fission products in the
form of inert gases: helium, argon, xenon, etc. Having a
low solubility in metals, they form helium-vacancy bub-
bles. In [5], it was found that in the U-Mo alloy, in the
absence of recrystallization under irradiation, in bubbles
with an average size of about 2 nm, the internal pressure
can reach 800 MPa. Comparison of these values with the
tensile strength of the uranium-molybdenum alloy, tak-
ing into account its sharp decrease after irradiation,
makes the situation rather alarming from the point of
view of embrittlement.
3. MECHANISMS OF RADIATION
EMBRITTLEMENT
If we assume (taking into account Fig. 2) the presence
of three stages of embrittlement depending on burnup:
1 – burnup level up to 0.02%, when plasticity is
Fig. 2. Influence of the degree of burnupt under the
neutron irradiation on the deformation to failure (a) and
tensile strength (b) for natural uranium: ● – [7];
Δ – [8]; – [9]; ■ – [10, 11] and alloys
U (9…10)% Mo; – [12–14]. The irradiation tempera-
ture of all types of uranium samples did not exceed
140 °C. The test temperature is room temperature. The
arrow indicates the maximum burnup level of the NI NSC
KIPT uranium target for a year of operation at full
power. The level of deformation of non-irradiated sam-
ples is in the range of 9…19%
b
a
ISSN 1562-6016. ВАНТ. 2022. №2(138) 59
0.4…0.8%; 2 – “plato” for plasticity and 3 – “zero” plas-
ticity when burnup is over 0.1%, – then the failure mech-
anisms can be represented as follows.
Stage 1 embrittlement. The level of burnup is up to
0.02%, corresponds to doses of the order of tens and hun-
dreds of dpa. Under these conditions, the deformation of
irradiated materials with different types of crystal lattice
takes place under conditions of plastic instability associ-
ated with the effect of dislocation channeling – slip local-
ization in narrow regions less than a hundred angstroms
wide [17–19]. The mechanism of crack initiation is re-
lated to the concentration of stresses (σ) generated by the
interaction of localized slip bands having a large number
of similar dislocations (n) with grain boundaries (σ = nb,
where b is the value of the Burgers vector) (Fig. 3).
According to [15], the decisive factor in the embrit-
tlement of such uranium alloys at low temperatures is the
decrease in cohesive strength associated with a change in
the state of grain boundaries. In turn, the main type of
grain-boundary precipitates in uranium-molybdenum al-
loys are carbides.
Fig. 3. Pile-up process of interaction of localized slip
bands with precipitates at grain boundaries at burnup
levels corresponding to stage 1 of embrittlement. The
arrows mark the places of formation of vacancy-helium
pores on the surface of precipitates
In real U-Mo alloys, even in those smelted under the
conditions of vacuum arc remelting, the carbon content
in the matrix corresponds to values of the order of
(1...7) 10-2% [20]. Taking into account the important role
of carbon in the formation of the structure and properties
of uranium and its alloys, its concentration was deter-
mined corresponding to the formation of a monolayer at
the grain boundaries. It was assumed that the shape of the
grains is octahedral, and their size is at the level of
130…170 μm, which corresponds to the conditions for
optimal heat treatment [20]. As a result, it was found that
this concentration is at the level of (5…6) 10-3 %. Thus,
at the carbon concentrations indicated above, not only a
carbon monolayer can be located at the boundaries of ura-
nium grains, but carbides will also form, as noted, for ex-
ample, in [21], and as shown in Fig. 3.
The interface (uranium carbide)-U-Mo matrix has a
great influence on the mechanical stability of the material
under irradiation due to a significant difference in the
thermophysical characteristics of the carbide and alloy.
Thus, it was established that the interatomic bond formed
at the interface is rather weak, as a result of which it be-
comes the predominant site of nucleation for vacancy-he-
lium bubbles [22].
These processes can lead to a sharp decrease in the
effective surface energy of the boundaries and, as a con-
sequence, to a decrease in the critical fracture stress (ac-
cording to the modified Straw criterion [16]). The same
patterns are observed in U-(7…9%) Mo alloys in the
non-irradiated state: intercrystalline fracture associated
with grain-boundary carbon segregations, which reduce
its cohesive strength [15].
The second – transitional stage – (“plateau”) is a
kind of incubation period for the origin of grain-boundary
porosity on carbides. Under these conditions, when the
fracture stress (up to 500 MPa, Fig. 2,b) is significantly
higher than the yield strength, plastic deformation can
take place, which means that there should not be com-
plete embrittlement
At the 3 – “zero” stage, embrittlement is determined
by a significant loss of strength Fig. 2,b, and destruction
in the elastic region associated with a change in volume
due to an increase in volume ΔV/V, (especially due to its
local change at the grain boundaries in where they inter-
act with localized slip bands). The expression for the ex-
perimentally determined tensile strength of samples σf of
the irradiated material, taking into account Hooke's law,
can be represented in the following form:
σf = σо –
Е
3(1−2𝜐)
ΔV/V,
where σo is the tensile strength of the non-irradiated ma-
terial, υ is Poisson's ratio.
With an increase in the level of burnup, and the cor-
responding concentration of vacancies and gas impuri-
ties, the process of combining cavities associated with
grain boundary carbides (the so-called debonding) (see
Fig. 3) can occur, under the action of applied stresses,
due to the deformation elimination of bridges between
the pores, followed by formation of microcrack nuclei.
Thus, the ultimate tensile strength under irradiation de-
creases as internal stresses increase, proportional to the
expansion of the crystal lattice, and as the stress concen-
tration at the grain boundaries increases.
Where does the increase in the volume of uranium
and its alloys come from? Usually, the volume of nuclei
of fission products is greater than the volume of uranium
nuclei from which they were formed [16]. This circum-
stance leads to the so-called “solid” swelling. The effect
does not depend on the irradiation temperature and for
alpha-uranium gives an increase in volume of the order
of 3…4% per 1 atomic percent burnup [23].
What values of ΔV/V are necessary to create brittle
fracture conditions for reactor materials irradiated to high
doses? The answer to this question is the results of [16],
in which it was found that a volume change of about 7%
leads to the destruction of irradiated austenitic stainless
steels during mechanical tensile tests at room tempera-
tures in the elastic region of deformations.
A comparative analysis of the dependence of radia-
tion hardening on the fluence and dose of irradiation of
uranium and structural materials showed that despite the
large difference in the values of neutron fluences (respec-
tively, 1015…1016 n/cm2 for uranium [15], and about
1020 n/cm2 for structural materials [18]), the saturation
level of radiation hardening (at test temperatures not ex-
ceeding 0.25 Tm) corresponds to doses of the order of
0.1 dpa. The same regularity is also observed during
60 ISSN 1562-6016. ВАНТ. 2022. №2(138)
mechanical testing of structural materials irradiated with
high-energy electrons with an energy of the order of sev-
eral hundred MeV, i.e. under conditions close to the op-
erating parameters of the target NPT NSC KIPT [24].
For natural uranium irradiated in reactors, doses of
the order of 0.1 dpa correspond to a burnup of
210-6…10-5 %. According to the results of [25], it is these
values that correspond to the effect of saturation of the
density of clusters of radiation defects, which have a de-
cisive effect on the radiation hardening of the material.
This confirms the decisive role in hardening (and hence
in embrittlement, given their direct relationship), namely
the level of damage to the material - the concentration of
point defects and their complexes.
It was found in [26, 27] that in plate nuclear fuel for
experimental and research reactors made of U-10% Mo
alloy, surrounded by a coating of 6061 alloy (analogous
to SAV), even at extremely high (for this type of fuel)
burnup levels (tens of percent) and gas swelling (up to
76%!), despite the destruction of uranium fuel plates, due
to the aluminum coating, the mechanical integrity of the
fuel elements is maintained.
The situation when the structural materials of nuclear
installations operate practically in a brittle state is not
new for reactor materials science. So, for example, solid-
state targets of existing megawatt ADSs – such as ISIS
[28], LANCE [29], the facility under construction in
Lund (Sweden) [30], as well as the facility controlled by
the high-energy electron accelerator (100 MeV) 100 kW
at NSC KIPT, from the very beginning work uses tung-
sten targets at operating temperatures well below the brit-
tle-ductile transition temperature of these materials.
Under these conditions, of great importance is the
analysis of the parameters of high-cycle fatigue of the tar-
get plates under conditions close to the parameters of the
NPT KIPT target. Such an analysis was carried out in
[31]. It was shown that for uranium the endurance limit
under high-cycle fatigue (up to 2 107 cycles) is on the or-
der of 100 MPa. Comparison of this value with the frac-
ture stress of uranium and uranium-molybdenum alloy
(see Fig. 2,b) shows that the service life of a uranium tar-
get cannot exceed 9 years of continuous operation. In ad-
dition to the high-cycle fatigue limit, one should also sub-
tract the “third stage” of the unstable dependence of em-
brittlement at burnups greater than 0.2%. This gives such
a target a service life of 3 years of continuous irradiation.
CONCLUSION
1. Analysis of the results of mechanical testing of ura-
nium and uranium-molybdenum alloys showed that such
levels of damage (burnup) can lead to almost complete
embrittlement of the target material. At the same time,
the advantages of the uranium-molybdenum alloy over
natural uranium in terms of plastic characteristics are
practically not observed.
2. The dependence of the degradation of strength and
plastic properties on the level of uranium burnup is con-
structed, which consists of three stages: the first – up to
burnup of the order of 0.01%, when plastic flow occurs
in the irradiated material and an increase in the yield
strength is observed, the second – at burnup of
0.01...0.1%, (“plateau”) mechanical properties are
weakly dependent on burnup, and the third stage is at
burnup of more than 0.1%, when softening is observed
and a transition to fracture occurs in the elastic region of
deformations.
3. A description of the processes of radiation embrit-
tlement is presented, taking into account the deformation
and porosity of materials at various levels of burnout.
4. A sharp decrease in the characteristics of plasticity
and strength, uranium and uranium-molybdenum alloys,
even at burnup levels of several tenths of a percent, can
cause a violation of the mechanical integrity of the target
plates. However, under conditions of maintaining the
continuity of the coating of aluminum alloy SAV-1, this
effect will not lead to a change in the performance of the
target.
5. An estimate of the expected service life of a ura-
nium target under irradiation has been carried out. Taking
into account the influence of high-cycle fatigue and the
dependence of embrittlement at burnup greater than
0.2%, gives the value of the target's service life of 3 years
at full accelerator power.
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Article received 01.04.2022
ВИГОРЯННЯ ТА РАДІАЦІЙНА КРИХКІСТЬ U-Mo-МІШЕНІ ДЖЕРЕЛА НЕЙТРОНІВ
Б.В. Борц, В.В. Ганн, А.Ю. Зелінський, О.О. Пархоменко, О.Ф. Ванжа, Ю.А. Марченко, І.В. Паточкін
Досліджено вигоряння уранових мішеней джерела нейтронів ННЦ ХФТІ. Проведено аналіз експеримен-
тальних робіт по впливу нейтронного опромінення на міцнісні та пластичні властивості урану і сплаву U-Mo
в умовах, наближених до умов роботи мішені. Проведена оцінка очікуємого ресурсу роботи пластин уранової
мішені під опроміненням.
ВЫГОРАНИЕ И РАДИАЦИОННОЕ ОХРУПЧИВАНИЕ
U-Mo-МИШЕНИ НЕЙТРОННОГО ИСТОЧНИКА
Б.В. Борц, В.В. Ганн, А.Ю. Зелинский, А.А. Пархоменко, А.Ф. Ванжа, Ю.А. Марченко, И.В. Паточкин
Исследовано выгорание урановых мишеней источника нейтронов ННЦ ХФТИ. Проведен анализ экспе-
риментальных работ по влиянию нейтронного облучения на прочностные и пластическиe свойства урана и
сплава U-Mo в условиях, приближенных к условиям работы мишени. Проведена оценка ожидаемого ресурса
работы пластин урановой мишени под облучением.
http://dx.doi.org/10
http://dx.doi.org/10.1016/B978-0-12-803581-8.12067-3
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| id | nasplib_isofts_kiev_ua-123456789-195949 |
| institution | Digital Library of Periodicals of National Academy of Sciences of Ukraine |
| issn | 1562-6016 |
| language | English |
| last_indexed | 2025-11-24T11:40:31Z |
| publishDate | 2022 |
| publisher | Національний науковий центр «Харківський фізико-технічний інститут» НАН України |
| record_format | dspace |
| spelling | Borts, B.V. Gann, V.V. Zelinsky, A.Yu. Parkhomenko, A.A. Vanzha, A.F. Marchenko, Yu.A. Patochkin, I.V. 2023-12-08T14:15:30Z 2023-12-08T14:15:30Z 2022 Burnup and radiation embrittlement of the U-Mo neutron source target / B.V. Borts, V.V. Gann, A.Yu. Zelinsky, A.A. Parkhomenko, A.F. Vanzha, Yu.A. Marchenko, I.V. Patochkin // Problems of Atomic Science and Technology. — 2022. — № 2. — С. 57-61. — Бібліогр.: 31 назв. — англ. 1562-6016 DOI: https://doi.org/10.46813/2022-138-057 https://nasplib.isofts.kiev.ua/handle/123456789/195949 669.18.2 The burnup of uranium target plates of the NSC KIPT neutron source was studied. An analysis of experimental work on the effect of neutron irradiation on the strength and plastic properties of uranium and U-Mo alloys under conditions close to the operation of the target has been carried out. A description of the processes of radiation embrittlement is presented, taking into account the deformation and porosity of materials at various levels of burnup. An estimate of the expected service life of a uranium target under irradiation has been carried out. Досліджено вигоряння уранових мішеней джерела нейтронів ННЦ ХФТІ. Проведено аналіз експериментальних робіт по впливу нейтронного опромінення на міцнісні та пластичні властивості урану і сплаву U-Mo в умовах, наближених до умов роботи мішені. Проведена оцінка очікуємого ресурсу роботи пластин уранової мішені під опроміненням. Исследовано выгорание урановых мишеней источника нейтронов ННЦ ХФТИ. Проведен анализ экспериментальных работ по влиянию нейтронного облучения на прочностные и пластическиe свойства урана и сплава U-Mo в условиях, приближенных к условиям работы мишени. Проведена оценка ожидаемого ресурса работы пластин урановой мишени под облучением. en Національний науковий центр «Харківський фізико-технічний інститут» НАН України Вопросы атомной науки и техники Thermal and fast reactor materials Burnup and radiation embrittlement of the U-Mo neutron source target Вигоряння та радіаційна крихкість U-Mo-мішені джерела нейтронів Выгорание и радиационное охрупчивание U-Mo-мишеней нейтронного источника Article published earlier |
| spellingShingle | Burnup and radiation embrittlement of the U-Mo neutron source target Borts, B.V. Gann, V.V. Zelinsky, A.Yu. Parkhomenko, A.A. Vanzha, A.F. Marchenko, Yu.A. Patochkin, I.V. Thermal and fast reactor materials |
| title | Burnup and radiation embrittlement of the U-Mo neutron source target |
| title_alt | Вигоряння та радіаційна крихкість U-Mo-мішені джерела нейтронів Выгорание и радиационное охрупчивание U-Mo-мишеней нейтронного источника |
| title_full | Burnup and radiation embrittlement of the U-Mo neutron source target |
| title_fullStr | Burnup and radiation embrittlement of the U-Mo neutron source target |
| title_full_unstemmed | Burnup and radiation embrittlement of the U-Mo neutron source target |
| title_short | Burnup and radiation embrittlement of the U-Mo neutron source target |
| title_sort | burnup and radiation embrittlement of the u-mo neutron source target |
| topic | Thermal and fast reactor materials |
| topic_facet | Thermal and fast reactor materials |
| url | https://nasplib.isofts.kiev.ua/handle/123456789/195949 |
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