The physics scale model project of two-cascade power blanket for electronuclear reactor
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| Zitieren: | The physics scale model project of two-cascade power blanket for electronuclear reactor / N.V. Zavyalov, V.F. Kolesov, A.V. Telnov, Yu.A. Khokhlov // Вопросы атомной науки и техники. — 1999. — № 4. — С. 8-10. — Бібліогр.: 14 назв. — англ. |
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irk-123456789-815122015-05-18T03:02:29Z The physics scale model project of two-cascade power blanket for electronuclear reactor Zavyalov, N.V. Kolesov, V.F. Telnov, A.V. Khokhlov, Yu.A. 1999 Article The physics scale model project of two-cascade power blanket for electronuclear reactor / N.V. Zavyalov, V.F. Kolesov, A.V. Telnov, Yu.A. Khokhlov // Вопросы атомной науки и техники. — 1999. — № 4. — С. 8-10. — Бібліогр.: 14 назв. — англ. 1562-6016 http://dspace.nbuv.gov.ua/handle/123456789/81512 en Вопросы атомной науки и техники Національний науковий центр «Харківський фізико-технічний інститут» НАН України |
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Zavyalov, N.V. Kolesov, V.F. Telnov, A.V. Khokhlov, Yu.A. |
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Zavyalov, N.V. Kolesov, V.F. Telnov, A.V. Khokhlov, Yu.A. The physics scale model project of two-cascade power blanket for electronuclear reactor Вопросы атомной науки и техники |
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Zavyalov, N.V. Kolesov, V.F. Telnov, A.V. Khokhlov, Yu.A. |
| author_sort |
Zavyalov, N.V. |
| title |
The physics scale model project of two-cascade power blanket for electronuclear reactor |
| title_short |
The physics scale model project of two-cascade power blanket for electronuclear reactor |
| title_full |
The physics scale model project of two-cascade power blanket for electronuclear reactor |
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The physics scale model project of two-cascade power blanket for electronuclear reactor |
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The physics scale model project of two-cascade power blanket for electronuclear reactor |
| title_sort |
physics scale model project of two-cascade power blanket for electronuclear reactor |
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Національний науковий центр «Харківський фізико-технічний інститут» НАН України |
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1999 |
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http://dspace.nbuv.gov.ua/handle/123456789/81512 |
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The physics scale model project of two-cascade power blanket for electronuclear reactor / N.V. Zavyalov, V.F. Kolesov, A.V. Telnov, Yu.A. Khokhlov // Вопросы атомной науки и техники. — 1999. — № 4. — С. 8-10. — Бібліогр.: 14 назв. — англ. |
| series |
Вопросы атомной науки и техники |
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THE PHYSICS SCALE MODEL PROJECT OF TWO-CASCADE POWER
BLANKET FOR ELECTRONUCLEAR REACTOR
N.V. Zavyalov, V.F. Kolesov, A.V. Telnov, Yu.A. Khokhlov
Russian Federal Nuclear Center – All-Russia Scientific Research Institute of Experimental
Physics, Sarov, Nizhni Novgorod region, Russian Federation
A danger of non-controlled power increase on
selfcritical atomic power stations and low economy of
nuclear fuel used in them (in energy release there
participate practically only isotope 235U whose nature
uranium fraction constitutes 0.72%) assign a priority to
creating principally new free from explosion accidents
subcritical reactors with a significant increase of nuclear
fuel “combustion” fraction in them.
Yet since 50-s years the world scientific
community have been considering going over to
electronuclear facilities with a subcritical core (blanket)
as one of possible ways for rising safety of nuclear
power facilities (NPF) [1-6]. In this case NPF core
operates in a mode of enhancing the neutron flux of
external source supplied by a particle accelerator. Going
over to electronuclear facilities allows to significantly
decrease a probability for reactivity accidents
occurrence and simplify the reactor power control, as in
this case it may be performed through the change of
particle current in the accelerator.
The main difficulty in the way of electronuclear
facilities implementation consists in too high require-
ments to accelerator power. For this purpose there are
required, for example, proton beams of (40-100) MW.
Lowering of requirements to the accelerator
power, as it was shown in papers [7, 8], can be reached
on the basis of using two-cascade blankets with cascade
one-way neutron coupling, i.e. using diode blankets.
From the mentioned papers there follows that the
property of unidirectional conduction of cascade
neutron coupling is major at this process. The factor of
blankets two-cascade structure brings no advantages
without it. In all cases, in order to benefit significantly
by going over to a two-cascade structure of blankets,
there is necessary to provide a high (on 100-1000 - fold
level) relation of factors of cascade coupling.
Physically, the most efficient method to create a
cascade diode coupling was proposed at VNIIEF [9].
This method is based on application of threshold fissile
material - neptunium-237 in one of cascades and
separation of cascades by a neutron moderator layer.
Initially, the method was oriented to applications in the
field of pulsed boosters serving as neutron irradiators.
Development of these devices faces the difficulties,
similar to those in case of electronuclear power
facilities, as the generation of neutron pulses with short
duration in boosters necessary for irradiating
experiments usually needs very powerful pulsed
electron accelerators. Basing on the mentioned proposal,
at VNIIEF in Russia and in Sandia National
Laboratories in the USA there were developed designs
of irradiating boosters with unique parameters [10, 11].
Boosters taking the two-cascade structure with cascade
diode coupling allowed (according to calculations) to
decrease abruptly neutron pulses duration (at invariable
accelerator power).
Basing on the proposals and analysis of papers
[9, 12], in the early eighties there was developed in
VNIIEF a design of booster-reactor "Kaskad" (BR-K)
with the internal core made of 237Np- + Ga alloy and
the external core – of uranium-molybdenum alloy [10].
It was supposed that BR-K would operate combined
with high-current electron accelerator LIU-30 [13]
which is to provide the core of neptunium-237 with
1·1015 primary neutrons per 20-100 ns long pulse. In
the design of BR-K there are taken into account to a
maximum extent the requirements conditioned by the
desire to get possibly highest values of neutron fluence
and gamma-radiation dose per pulse at points of
samples irradiation, larger volume of irradiation cavities
and to make easier the access to the places of samples
irradiation. The selection of cylindrical booster-reactor
geometry, horizontal orientation of its axis, degree of
uranium enrichment in the external core, volume and
configuration of internal cavity was governed by the
above requirements.
Basic elements of BR-K design are presented on
Fig.1. BR-K has a cylindrical shape with coaxial
arrangement of internal and external cores, layer of
tungsten, accelerator target and cavity for irradiation.
The axis direction is horizontal.
The internal core (core-1) is made of alloy of
237Np with 9% of gallium by mass. The diameter and
length of core 1 are correspondingly equal to 23 and
~25 cm. The full mass of alloy in core 1 constitutes
120-130 kg. Core 1 is collected of cylindrical
components 0-6, 6-16 and 16-23 cm in diameter and
~8 cm long.
The external core (core 2) is made of alloy of
uranium (36% -enrichment by 235U) and 9% of
molybdenum by mass; it has a form of a hollow cylinder
105 cm long with a maximum external diameter
~70 cm, diameter and length of the channel for
irradiation is equal to 36,5 cm (the dimensions are
specified by fuel. The total mass of alloy in core 2 is
equal to ~2400 kg.
The space between core 1 and core 2 is filled
with tungsten (to be more precise - with the alloy of
tungsten, nickel and copper; mass content: tungsten -
95%, nickel - 3%, copper - 2%) of 18,0 g/cm3 density.
It should be mentioned, that all known papers on diode
two-cascade systems refer to calculation-theoretical or
design ones. The experiments on diode systems have
been conducted nowhere till now. Theoretical
conclusions on diode cascade systems properties are to
be proved experimentally.
BR-K VIEW IN AXIAL SECTION [10]
Performance of this type experiments is one of
main tasks of the proposed investigations. The planned
experiments will aim, first of all, at affirmation of
reality of information on strong suppression of one of
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cascade neutron coupling factors due to neptunium-237
employment as well as to the fact that strong
suppression of one of coupling factors really raises
electronuclear facility efficiency.
Fig. 1.
1 - reflector of neutrons; 2 - regulating block of core
2 (RB-2); 3 - mobile block of core 2 (MB-2);
4 - emergency block (EB); 5 - immobile block of core
2 (IB -2); 6 - regulating block of core 1 (RB-1); 7 - stop-
block (SB) and pulse block (PB-2); 8 - channel for
bremsstrahlung run; 9 - 6LiH-type neutron moderator;
10 - mobile block of core 1 (MB-1); 11 - pulse block of
core 1 (PB-1); 12 - immobile block of core 1 (IB-1);
13 - tungsten massif; 14 - container for irradiated
samples.
At present at our institute there are planned
investigations of physics blanket neptunium cascade
model. As a primary neutron generator it is supposed to
use a target of the electron linear accelerator LU-50
[14], operating at VNIIEF; the neutron yield from this
target can be brought up to 1014 n/sec. The accelerator is
designed to operate continuously in the mode of
generation of neutron pulses with a different amplitude
and repetition frequency up to 2400 Hz.
As a result of a large number of calculations
conducted under Monte-Carlo programs there were
grounded the most rational configurations of diode two-
cascade blanket models, suitable for carrying out
experiments under the Project. There were selected
blanket configurations using comparatively small fissile
materials amounts and known to satisfy nuclear safety
requirements without taking special safety measures
(Fig.2).
Besides the above-mentioned arguments, the
expediency of low keff value assemblies employment in
the planned experiments is also proved by the fact that
exactly on such assemblies type there is possible to
compare directly data of experiment and numerical
calculation. As it is shown in paper [8], the direct
calculation of keff and total numbers of diode blanket
fissions with the help of modern Monte-Carlo programs,
in the case of blankets with large value of keff (>0.9), is
extremely difficult. In this case, keff and total fission
numbers are calculated with the aid of theoretical
formula of relationship between these magnitudes and
easily calculated factors of neutron multiplication in
cascades keff1, keff2 and factors of cascade neutron
coupling k12, k21.
Model assemblies with low keff planned for executing
experiments
а
а
1
2
3
a
1
3
4
b
3
c
a - two-cascade assembly with an intermediate
moderator layer; b - two-cascade assembly without an
intermediate moderator layer; c - one-cascade assembly;
1 - neptunium-237; 2 - polyethylene; 3 - high-enriched
uranium; 4 - vacuum.
Diagrams of model assemblies with keff=0.53
Neutron
source
0 2,9 8,0 9,07 cm
__________________________________
Neptunium-237 Polyethylene Uranium
ρ = 20,45 ρ = 0,92 ρ = 18,7 g/ cm3
М = 2 kg М = 18,0 kg
235U - 90%
238U - 10%
Neutron
source
0 2,9 8,0 9,80 cm
__________________________________
Neptunium-237 Vacuum Uranium
ρ = 20,45 ρ = 18,7 g/ cm3
М = 2 kg М = 33,6 kg
235U – 90%
238U – 10%
Neutron source
0 4,53 cm
_____________________
Uranium
ρ = 18,7 g/ cm3
М = 7,28 kg
235U – 90%
238U – 10%
Fig.2.
In the experiments there will be measured the
factors of section neutron coupling k12, k21 and, what is
more important, absolute spatial distributions of fissions
density in sections allowing to determine total numbers
of fissions in cascades and assemblies in the aggregate,
with normalization per one source neutron. The data of
measurements on two-cascade assemblies will be
compared to similar measurements on one-cascade
assemblies. At this process, an important requirement is
maintenance of equality of keff of assemblies. Removal
of intermediate layer diminishes the magnitude of
cascade coupling factors relation, but, however, in this
case the assembly also remains a two-cascade diode
one. The intermediate layer removal may be
ВОПРОСЫ АТОМНОЙ НАУКИ И ТЕХНИКИ. 1999. № 4.
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8
compensated through a change of uranium layer
thickness or by an external reflector.
The computations testify to acceptability of these
assemblies with low keff values as a base for conducting
the planned experiments. The difference in efficiencies
of one-cascade and diode two-cascade blankets is not
large in this case, but, however, it is quite enough to be
noted in the experiment. The aforesaid is proved by data
for the models with keff =0.53. Total fission numbers in
these blanket models, referred to one neutron of a
central source with a fission spectrum, are equal to 1.26;
0.803 and 0.633. This means that efficiency of the two-
cascade diode blanket models is 1.99 and 1.27 times
higher than that of the one-cascade blanket (cascade
coupling factors k21,k12 in the upper assembly and the
following one equal, relatively: 0.657; 0.0078 and
0.337; 0.017).
In spite of small masses of used fissile materials
and, correspondingly, low levels of keff neutron
multiplying factors, these blanket configurations
provide a possibility for precise experiment recording of
quantitative indexes of these models of diode two-
cascade blanket as compared to common blankets
indexes. As expected, the experimentally obtained data
will directly prove the rightness of theoretical
knowledge on diode blankets advantages and will serve
a reliable benchmark base for correcting calculation
methods.
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Серия: Ядерно-физические исследования (35), с. 8-10.
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