JPRS ID: 9829 USSR REPORT ENERGY

• Document Type: CREST
• Collection: JPRS
• Document Number (FOIA) /ESDN (CREST): CIA-RDP82-00850R000400030010-3
• Release Decision: RIF
• Original Classification: U
• Document Page Count: 22
• Document Creation Date: November 1, 2016
• Sequence Number: 10
• Content Type: REPORTS

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JPRS L/9829
8 July 1981
- USSR Re ort
p
_ fNERGY
CFOUO 9/81)
F~IS FOREIGN BROADCAST INFORMATION SERVICE -
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JPRS Y,/9829
8 July 1981
_ USSR REPORT
ENERGY
(FOUO 9/81)
CONTENTS
ELECTRIC POWER
_ Work Continues on Construction of Chernobyl'skaya AES
(V. S. Konviz; ENERGETICHESKOYE STROITEL'STVO, Apr 81) 1
FUELS
Blue Gold of West Siberia
(Sab~t Atayevich Orudzhev; GOLUBOYE ZOLOTO `LAPAUNOY
SIBIRI, 1981) 8
~ Results, Prospects of Petroleum Refini:Zg, Petrochemical
Industry Summarized
(M. F. Sisin; EKONOMIKA, ORGANIZATSIYA I UPRAVLENIYE
V NEFTEPERERABATYVAYUSHCHEY I NF.~'PTEKHIMICHESKOY
PROMYSHLEDTNOSTI, No 2, 1981) 13
3;
- a - [III - USSR - 37 FOUO]
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FOR OFFI('IA1. IISE ONI.Y
ELECTRIC PUTnJER
WORK CONTINUES ON CONSTRUCTION OF CHERNOBYL'SKAYA AES
Moscow ENERGETICHESKOYE STROITEL'STVO in Russian No 4, Agr 81 pp 2-6
[Article by candidate of technical sciences V. S. Konviz: "The Second Phase of
the Chernobyl'skaya AES"J
[Text] At the present time, work is being conducted at the site of the
Chernobyl'skaya AES on installations of the second phase of construction, while
the third phase has already bpen begun. The second phase will have the same output
~ as the first, which was basically completed in 1978 and which has two generating
sets with 1,000-MW RBMK [high-output, channel-type] reactors. With the commission-
in g of this second phase, the electric station's output will reach 6 million kW.
,
Since matters regarding the design and construction of the f irst phase of the
Chernobyl'skaya have been systematically covered [1-4], we will note only the high
operational characteristics ~f this el~ctric power station. No more than six months
are required to bring power units with RBMK-1000 reactors up to rated power. As
early as a year after the rea~tors were brought up to rated power, the utilization
factor of their rated capacity reaehed 75 percent, while the operational readiness
factor exceeded 90 percent.
The basic production equipment utilized in the f irst power units is being installed
in the second phase of the AES.
In the design of the second phase, however, the speed of response and the perform-
ance of the reactor's emergency coolin g systems have been considerably improved.
For complete condensation of steam leaking from the circuit during possible emer-
gencies associated with a rupture of the largest pipes i:~ the loop used foL circu-
lation of the heat-transfer medium, provisions have been made for a bubbler basin
located directly under the rigid leakproof chambers of the heat-transfer medium
circulation loop. Steam can be taken up into this basin in case the main safety
valves on the steam lines are actuated. Such a solution excluded the necessity
of installing bubblers in the machine room with its compla.cated asSembly of inedium-
pressure pipelines.
The reliability of the electric circuits and the power supply systems for internal
AES needs has been improved.
1
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The performance of the central heating installation has been increased almost two-
fold (to 1,470 GJ/h) which will make it possible to provide heat to population cen-
ters located in the immediate vicinity of the AES, to hothouses, etc.
In the design, a great deal of attention has been devoted to questions of prote~ting
- the environment. We will note in particular that the efficiency of the purifying
equipment has been increased as well as that of the systems for suppressing the
radioactivity of aerosol wastes an~ for special water purif ication. The capacity
of sewage decontamination equipment has been doubled and provisions have been r~ade
for f inal purif ication of sewage in sand f ilters.
Atomic electric power stations in general and those with RBMK reactors in particular
belong to the must labor-intensive installations in power-plant construction. In
connectian with this, designers and builders devote 3 great deal of attention to
the problem of reducing the labor expended during the installation of construction
and installation operations.
At atomic electric power stations with RBMK reactors, the most labor-intensive oper-
ation is t:~e construction of massive concrete safety structures. Since these elec-
tric stations are single-circuit, sucn structures are characteristic not only of
the reactor chamber and special buildings at the construction site, but also of
thz machine room where the turbine unit, condenser-purif ier, condenser-supply cir-
cuit and deaerator are enclosed by massive concrete shielding.
During the construction of the first phase of the Chernobyl'skaya AES, the protec-
tive structures were made from cast-in-situ rei.nforced concrete. The complexity
of erecting these structures increased because it was impossible to use large-
diameter sheathing and difficult to insure a good-~ua.lity facing surface due to
the large numb ~r of engineering shafts and embedded structural elements. Assoc iated
with this, about 200,000 m2 of concrete surface on each power unit had to be plas-
tered before the spec ial protective covering was applied. A considerable portion
of the partitions and walls were made f rom brick and these were also plastered.
In order to re~uce the amount of labor expended and ttie length of tin~a needed to
erect such structures, it was necessary during the second phase of the construction
of the AES t~ make maximum utilization of precast and prefabricated cast-in-situ
reinforced concrete structural members as well as to reduce the number of individu-
ally standing buildings at the cons~ruction site and the number of operational lines
between them and the main building. However, the complex conf iguration of the
framework of the AES ?~uildings and the lack of standardization in structural dimen-
sions have hindered the application of precast and prefabricated cast-in-situ struc-
tural elements. The ordering of three-dimensional layout solutions for the main
building was complicated by the fact that the selection of the basic production
~ equipment and~the arrangement of the nuclear steam-generating installation in the
second phase af constrL~tion had to be retained without changes, that is, the same
as in the previous stage.
It was particularly difficult to do this in the reactor section, since the reactor
units, the special water-purification unit separating them and the repair unit had
different ttiree-dimensional layouts and were constructed f rom different structural
elements.
2
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The overall width of the reactor unit (72 m) and the width of its central room
(24 m) were used as the determining dimensions in the designs of the reactor
sections. The reactor units (retaining the layout of the nuclear assembly and the
transportation equipment) were turned to face one another. The remaining systems
of the reactor section were located b etween them with all dimensions in the plan
reduced to the dimensions of the construction grid by a factor of 3 m. At the same
time, the equipment for special water purif ication and the gas systems were located
in the lower portion cf ~he building. The repair shops for "dirty" equipment in
the middle section and the exhaust ventilating system with compartments for f ilters
and the unit for suppressing the r.adioactivity of aerosol wastes (UPAK), previously
Iocated in a separate building, were located in the upper portion.
Immediately over the exhaust fan station on the roof of the building was installed
a ventilatiun stack. Such a solution eliminated the necessity of constructing cum-
bersome ventilation boxes on the bridge between the main building, the ventilation
- stack and the UPAK.
A transport-engineering.corridor was made along the outer perimeter of the reactor
section at a height of 12.5 m. Large-scale equipment can be brought in along this
corridor into the repair area and up to the rail approaches.
As we already know, the bedplate for the reactor section in the f irst phase of the
AES was lowered to a depth of 8 m, while large areaways were situated even lower,
- to a depth of 13.5 m. Only after installing these areaways, which took more than
six months, were we able to get on with erecting the reactor unit proper. Consider-
able difficulties arose during the waterproofing of the building's underground con-
_ tour, upon which great demands are made.
In the design for the main building in the second phase of the AES, the flat bed-
plate of the reactor compartment was put on the same level as the areaways. The
entire building was raised over the level cf the ground water, in connFCt3on with
, whicti the height of the building's above-ground portion was increased.
The new layout of the main building pro~ides fo"r locating immediately alongsic~~
its rear facade the reservoirs for collecting the drain water, tanks for clean and
contaminated condensate, a number of auxiliary systems which previausly had been
located on the production platform as well as newly created quick-response emergency
coolin~ systems for the reactors.
Out of the special structures on the production pla~form, only *_he storage facility
for radioactive wastes with its bitumenizing apparatus, connected to the main build-
_ ing by a trarisport and engineering bridge, is located separately. As a result,
the so-called "dirty" zone with its several small free-standing b uildings and struc-
tures has been eliminated from the general layout of the production platform.
As was already noted, in the new layout f or the reactor compartment we have managed
to regulate considerably the dimensions of the individual compartments and the floor
plan of the building as a whole. The vertical dimensions of the majority of com-
partments, however, were not changed due to the necessi*yo uf retain ing the arrange-
ment of the reactor unit while they, as a rule, do not correspond to the di~�