ML20058J517
| ML20058J517 | |
| Person / Time | |
|---|---|
| Issue date: | 08/23/1990 |
| From: | Richardson J, Stepanov I NRC, UNION OF SOVIET SOCIALIST REPUBLICS |
| To: | NRC |
| Shared Package | |
| ML20058J272 | List: |
| References | |
| JCCCNRS-WG-10, NUDOCS 9012020099 | |
| Download: ML20058J517 (38) | |
Text
_ - -.
I MEMORANDUM OF MEETING OF WORKING GROUP 10 1
EROSION /CORRCSION DESTRUCTION OF PIPING AND COMPONENTS INTRODUCTION 4
The Working Group met in Moscow ct the Kurchatov Institute of Atomic Energy and had a worthwhile and informative exchange of information.
The U.S. delegation was headed by J.E. Richardson, Director, Division of Engineering Technology, Office of Nuclear i
1 Reactor Regulation, Nuclear Regulatory Commission.
_The USSR participants were headed by I.A.Stepanov, Department Head, i
Research and Design, Institute of Power Engineering.
A-list of participants is shown in Appendix II.
Documents exchanged _are.
included in Appendix III.
The various topics of discussion focused on' methods of assuring the integrity of reactor systems th water chemistry, non-dGotructive examination, rough improvements in
, and the use of alternate new materials.
The specific _ topics discussed by the l
U.S. and the USSR participants covered the following:
i i
TOPIC 1:
WATER CHEMISTRY REGIMES FOR PRESSURIZED WATER (PWR):AND l
BOILING WATER (BWR) REACTORS IN NUCLEAR POWER PLANTS Scoce and Content of Discussions 1
The U.S. participants presented discussions on improvements in the composition and' control of the quality of water chemistry I
developed to prevent, deterioration of'the reactor system materials.
The U.S. presented summaries of the criteria and-standards developed for water quality for=BWRs and PWRs operating in the U.S. and improvements in water chemistry controls initiated to provide additional margins against material degradation.
Current cheinistry-guidelines _forEprimary and secondary systems were discussed.
In-the primary system the philosophy of pH control and its relationship to ALARA control was discussed.
A historical review of secondary side chemistry control was given including action level and numerical guidelines fc7 all aspects of operation.
On-line monitoring and computerized data management systems currently being used in U.S.
plants'were described in detail.
The addition of hydrogen to BWR water chemistry to protect against stress corrosion cracking of reactor piping and vessel internal components was discussed.
The USSR participants presented reports on RBMK and VVER reactors water quality normatives and on philosophy of primary system water radiolysis.
An important role is paid to developing corrosion monitoring systems including composition control and parametric coolant control, as well as electrochemical parametric 1
9012O20099 900823 PDR REVQP NROUS BR
~*"3C%
s IT
_ g_.
u.
structure materials control.
Effective methods for erosion-corrosion prevention is the' inhibiter application, for 1
example, octadecilaminium.
Conclusions It was noted that significant differences exist'in the established maximum levels-of chloride.in secondary side PWR water chemistry limits.
The USSR allows 160 ppb as an upper ~ limit to operate while the U.S. maintains the levels'at less than 20 ppb Chloride.
The USSR presented both field and-laboratory data on the use of Octadecylamine (ODA) to inhibit. erosion-corrosion in carbon and low alloy steels (single and to a lesser extent two phase flow).
The data indicate that an active erosion-corrosion process may be halted through additions of the ODA water treatment.
A rigorous thermodynamic treatise on Calcium Carbonate scale' formation disclosed-the concern the-Soviets have over scale formation on fuel rods in their. reactors.
The U.S. presentations indicated that both BWRs and PWRs have applied natiors11y recognized standards of water chemistry-controls and that many utilities in the U.S.-have-automated "on-line" monitoring and data acquisition systems in effect to control the water chemistry-within specified limits. - The General Electric presentation provided distinct correlations between water chemistry. controls and stress corrosion cracking propensity.
The Westinghouse presentation discussed the roatine use of hideout return data to establish prior cycle performance and the importance of its comparison to inspection data.
The USSR computer program developed two~ years ago to predict erosion-corrosion'has been updated and refined to. incorporate actual plant experience data.
It appears'to be very useful in predicting wall thinning from erosion-corrosion processes.
This program is compatible with the IBM PC.
A copy of this program will be provided to the USNRC.
It appeurs that USSR plants are proceeding in the same direction as U.S.. nuclear plants in the removal (wherever possible) of copper alloys from the balance of plant construction
~
materials and the raising of the feedwater pH to greater than 9.2.
The USSR polarization resistance device could be useful as an on-line monitoring system.
The USSR uses this device to measure the effectiveness of their water chemistry controls since they have measured a five fold increase in corrosion rate within the normal ranges of reactor operation.
Eventually, the device 2
'*9
-**"**W*&N..
,9 memus q p..:
7_,.,-.
. z,-
could be used to guide the operator in obtaining a more optima *.
chemistry operation of the plant.
.1 The All Union Institute ofLAtomic Power of Machine Buildin0 (VNIIAM) is involved in the design of steam generators, helium gas cooled reactors, purification of water equipment balance of-plant systems (nuclear plants), diagnostic systems, and reliability and safety of power plants.
The Institute is the primary facility for installing all test equipment in USSR nuclear reactors.
.This Institute is strongly recommendingLthe use of ODA for the mitigation of erosion-corrosion in.the secondary systems in nuclear units-(already tested-at the Nord and Kola units).- East Germany and Hungary-have already tested ODA and EdF is considering its use on French plants.. The Institute.is also developing technology for vertical steam 1
generators and has done preliminary testing on Incone11600' alloys.
The Kurchatov Institute has unique research reactor designated MR.
It has a 50 MW thermal output.
Its uniqueness lies in its ability to simultaneously test 10 water chemistry-regimens with 3 specimens / tests for a total run of 30 specimens.
One test channel has the flexibility of "on line" insertion of.
specimens during operation.
The reactor uses He*8 as the moderator surrounding the fuel elements of the core in order to study fuel elements under various load' levels.
The reactor flux l
is 2-3x10" N/cd with the. highest. flux developed in the.
l horizontal channels.
The reactor was commissioned in 1963:and the core is 600 mm high and 600 mm in diameter.
This reactor's experiments war.e the basis for qualification of all USSR reactor i
fuel.
This Institute develops water chemistry l specifications.for all UF 0 roactors (including VVER and RBMK).
The primary water chemit y specifications for the RBMK typically specifies50-70c,a of oxygen which is significantly lower than the U.S.
BWRs. which typically specify oxygen in the 200-300 ppb range.
The Inst 1tute is currently investigating the possibility of introducing hydrogen water chemistry to the USSR RBMK reactors.
The VVER uses. ammonium-potassium with boric acid'(high temperature pH 6.g-7.1)'and 30-60 cc/kg hydrogen concentration as the primary water chemistry.
The USSR is investigating zine compounds (other than zinc oxide) for oxygen scavenging in order to provide a dual purpose addition (e.g., general-corrosion inhibitors) in the VVER primary coolant' loop.
TOPIC 2:
SEPARATION AND' TRANSPORT OF' CORROSIVE PRODUCTS ScoDe and Content of Discussions The U.S. participants presented discussions of the problem of corrosion product release to reactor water.. transport, and t
L deposit with resultant radiation buildup that forms a principal 3
)
- 'W_19 9 4 v_M e'99%'X W :.,r'L a 3.ar..'
am, -
.e, a,
.~
---.m.,_.--
+, o.c n r -, -.
1.J l
i depos1t with resultant radiation but1 dup that forms a principal source of personnel radiation exposure.
The U.S. discussed-categories-of experiences of corrosion product transport in U.S.
plants, problems associated with these_ conditions.-and remedial' actions implemented to reduce. radiation buildup.
Mechanisms of corrosion of self-passivating metals were described, as was the control of radiation buildup.
The concept of injecting zine to reduce radiation buildup on BWR piping has developed and applied to six BWRs_with resulting low dose rates.
Several corrosion.
a product transport studies carried out in operating PWR plants in the U.S. were described.. The effects of sludge buildup in i
nuclear steam generators was discussed and associated corrosion:
phenomena reviewed.. A sludge management control program wasL presented with emphasis on-new chemistry programs to minimize sludge buildup.'
Results were-related to erosion and corrosion control in balance of plant systems.
The USSR participants presented experimental data on corrosion release and distribution products along:the steam-water
(
lines of the secondary loop of a VVER-10DD reactor and on 4
kinetics of salt hardness deposition on heat transfer surfaces.
Conclusions ODA (Octadecylamine) appears to mitigate chloride induced' crack propagation in laboratory stress corrosion cracking tests in addition to selectively extracting copper from solution during cleaning operations.
This selective extraction of copper ~and-the inhibition of iron transport would be of benefit in.the minimization of corrosion product transport (buildup).
ODA has also been shown to be of benefit in the lay-up of steam generators.
TOPIC 3:
NON-DESTRUCTIVE EXAMINATION TECHNIQUES'FOR MONITORING DEGRADATION OF COMPONENTS DUE TO EROSION AND CORROSION Scoce and Content of Discussions The U.S. participants presented discussions on their mutual 5
experiences-in the monitoring of piping and components for i
degradation caused by erosion-corrosion and other corrosion l
conditions such as stress corrosion crackira.
The U.S. described developments and experionces in non-destructive testing for wall thinning due to erosion-corrosion and for detecting intergranular stress corrosion cracking in piping.
The U.S. has performed.
parametric studies on:non-destructive examination (NDE) reliability and deve'ioped recommendations for. ensuring effective inspection through improved procedures and personnel qualification.
A piping inspection round1 robin established deficiencies in inspect 4 e reliability and led to American Society of-Mechanical-Er.
....srs ( ASME)Section XI Code 4
e y
_,,[,
[,, _
.-,,,....,_,y.
g...._,_,_,_...,...,,...,,.....r
7._. _. _..
_ ~. a.._._...-
1
....a
~
-1 developments on the qualification of NDE personnel-and '
i performance demonstration for ultrasonic' examination systems.
The U.S. presented data on non-destructive testing for. evaluating-l erosian-corrosion damage =in piping and components.~
The various techniques.for grid sizing, location of grids and ultrasonic i
methods of inspection were discussed.- Discussions of defect location in close proximity to weldments,-in addition to actual inspections on the Surry Unit 2 failed pipe was also presented.
l The USSR participants presented the. main trends on.
i non-destructive. control methods in testing equipment corrosion i
status including'various physical.. optical..and electrochemicsl l
methods with a number of new developments on control sensors.
. Temperatures control sensors with special-coatings have been-developed to ensure the lifetime serviceability under-the reactor i solat'en up to three to five years.
The accuracy of crack
.l detection in pipe lines measured by means-of acoustical emireion
)
is within 0.5 m at 100 m distance.
l t
Conclusions The U.S.
team visited the Research and Development: Institute of Machine Building Technology (CNIITMash)< including a visit to the corrosion studies laboratory and NDE laboratory.
The-Institute's mission is to solve materials problems and technology i
(not new designs).
The Institute is self-sufficient.
The Institute has three experimental plants where they produce their own manufactured equipment as needed (including ceramics and:
non-meta 11ics--no irradiated materials).
The NDE facility produces specialty transducers and x-ray equipment.-
The Research-and Development Institute of Power Enginepring i
(ENTEK) tour included an introductory film of the Inst 1tute a mission in addition to a film of the Chernobyl-disaster and an overview film of Soviet reactors.
Various-attendees at the meeting had participated during the Chernobyl crisis and recovery.
The Institute.is currently developing' thermal cassettes placed in graphite to-measure. temperature in order to i
prevent any future incident like Chernobyl.- The Institute is i
also developing in-line corrosion monitoring-devices for diagnostic applications.
The Institute has developed various diagnostic instruments of which 80 percent.could,be adopted to VVER reactors.
The sensore developed here are useable:up to l
350*C.
The USSR were extremely interested in how the U.S. was limiting cobalt additions in steels.
The USSR' limits cobalt to
.002.004 for "in-core" materials.
The Institute'is also developing tribology and exterior pipe coatings for reactor piping applications.
l 5
i
.c z., -
-7 L
TOPIC 4:
RESEARCH ON CORROSION-EROSION ALTERNATIVES OR NEW MATERIALS Scoce and Content of Discussions-The U.S. participants presented discussions on alternative I
or nLW materials being substituted for existing materials for.
which degradation has been observed.- The.U.S. presented a i
discussion of the extensive development and. qualification program' 1
performed to select materials _that mitigate _the problem of1 I
l intergranular stress corrosion cracking in mustenitic stainless steel.
As1a result,-Type 316NG was~ selected'as the preferred replacement material for cracked piping and,for use -in reactor:
internals.
The advantages and deficiencies'of this' material _were discussed.
Data was presented on Boric acid corrosion'of c:rbon steel reactor components.
A presentation of actual U.S.-reactor experience regarding wastage corrosion of bolts, pressure vessels and piping.with: emphasis on field corrosion rates.was made.
Laboratory data relative to corrosion rates in carbon steel.and, possible synergy of lubricant _ interaction was:also' discussed.
The U.S.
discussed the effect of alloying additions.of' chromium on steel to mitigate the.. problem of erosion-corrosion.
Two c
commercial chromium bearing low alloy steels have been recommended and are being used as replacement material'for excessively thinned components.
The use of austenitic stainless-steel has also been considered.
The advantages and special considerations of each were discussed.
The USSR side presented reports on studies of corrosion-mechanical resistance of reactor materials,'the:
l-mechanism of corrosion cracking, and.the investigation of cases where corrosion rupture of steam-generator pipe lines occurred.
4 Corrosion resistSnce of materials under operational' conditions were discussed.
Testing methods on erosion-corrosion were also discussed.
A number of models for erosion-corrosion-wear of carbon steel and nodule: corrosion of zirconium alloys have been developed.,The positive-experience of application of some new l
materials (i.e., new chromium and high nickel steels).that possess high corrosion has been considered.
A number of sealants that possess high corrosion / resistance and strength _ properties
~
under reactor radiation at t=300'C and-low cyclical-load.were presented lby the USSR.
l l
Conclusions i
.The-USSR presentation on wet steam' erosion-corrosion gave-expected results for chromium alloy concentration effects and appeared to show a direct relationship between corrosion rate and i
L relative humidity.
6 r
.aw ~.
..r,.,n,._,.._--,-+...,..
.a
-~
'-* :: :~.~. m.._... _..
- ~ r
. " ~
(
It was noted that the USSR has determined-an incubation-l period for nodular corrosion in zirconium alloys at RBMK' reactors at 400 effective reactor days of operation.
-The current USSR thermal heat treatments do not produce a
" fine grain structure" steel.. The Instituto of Metallurgy has a patent increasing the corrosion resistance-in plain carbon steel specifically in the erosion-corrosion regime.
It is worthy to note that U.S. type 316NG stainless steel has greater IGSCC' resistance'than type 347 Niobium. stabilized i
stainless steel under creviced cold work conditions.
Type 316NG stainless steel is a significant improvement over type 304 g!
and 316 stainless previously recommended for use in BWRs.
There are viable alternative-materials available to prevent erosion-corrosion in the secondary loops at nuclear power plants.
VISITS:
The U.S. delegation was invited to visit the-leading research and engineering centers of the USSR (Kurchatov's Atomic Institute. Institute of Power Engineering, Institute of Atomic Machinery, Research Institute of-Atomic Power Plants, Institute of Technology and Machinery, and the Research Institute "Prometei") and the Nuclear Power Plants of Leningrad and Zaporozhye.
The trends of the activities of the above-mentioned Institutes were discussed.
The USSR also presented summaries of newly developed materials, research methods, means for corrosion protection, and methods'for materials and equipment' Quality-control.
The U.S. delegation noted the large volume of valuable information presented by tne Soviet' side.
The' discussions with-the USSR specialists were exceptionally open and honest.
GENERAL CONCLUSIONS:
1.
The USSR has not experienced a steam generator tube rupture to date.
The USSR also. plugs tubes only'when leaks are discovered.
Differences in nondestructive test methodology brought to light show that the U.S. routinely uses Eddy-Current Testing (bobbin coil and rotating pancake) while the' Soviets have not fully explored this avenue of inspection.
2.
A major difference-in steam generator tubing materials composition was also discussed.
The USSR uses stainless steel while the U.S. uses Inconel 600 and is currently constructing steam generators with thermally treated Inconel 690 material.
Two units are currently operating with this new= material.
(-
7 t
---v.<
1 e e-m e -e e
.e s
,r.
er..,
l
-l 3.
It was noted that a new approach-to passive safety systems
(
was'being investigated _by theJSSR. employing jet pumps driven b/--
escaping steam to cool the-reactor core..The Soviet test rig (or-this is a fossil unit which is capable of'providing massive.rceam i
volumes for development of=large scale experimenta1' data, j
i 4.
The USSR has not yet applied" leak before breaa" in their i
reactor operations although various studies;of this criteria are being considered.
Applications.for " leak:before break" adoption-include an acoustic. monitoring system which can detect 2-3 liters / hour leakage with a 20.5 liter / hour error.
The transducers for the system can be up to-150 meters apart, r
depending on the signal to noise ratio in the area being
[
monitored.
l 5.
Since 1950 the Prometei InstituteLhas developed nuclear power materials for the entire nuclear power industry.
All-vessels and: ships and associated reactors were designed by the Institute.
The Institute' is structured to take an original iden j
for a reactor and has the capability to perform the i
engineering--tests and developmental work,Lspecification writing, and-all follow-up necessary up to the full operating life of the plant.
The Institute tests a broad spectrum of materials ranging in size from heavy cross sections to very thin wall material in order to evaluate the differences in the operating characteristics of the same material =.
The Institute tests a large assortment of material from pressure vessel steels to the i
more exotic alloys such as zircalloy and-titanium alloys.
The Institute has performed destructive testing of large-scale l
pressure vessels including pressure ~ vessel thermal shock experiments.
The corrosion loops encompassed a broad _ spectrum of environments with both static and' flowing systems in evidence.
A i
novel static simulation in a dynamic flow for testing turbine blades was. observed.
The USSR is currently developing new.
materials for advanced reactors in order to obtain a 70-year service life for the pressure vessel and appurtenances taking into account environmental effects, fatigue, and radiation-embrittlement.
For commercial reactor operations this was the most impressive unified facility seen in the USSR to date.
OVERAlL RECOMMENDATIONS:
1.
The participants agreed that there has been-an excellent working relationship. developed over the past two years between the U.S. and USSR members of the Working Group and both sides have benefitted from the exchanges.
It was agreed that, in accordance with the Protocol of the second meeting of the JCCCNRS, at the end of the 1990 program, which includes a visit to U.S.-plants and laboratories by the USSR,Lfuture work of Working Group 10 should be conducted within the framework of Working Group 8 and/or Working Group 9.
There are several 8
O
,[*,_
"$ -=
- -e--
' * * ~ * ' - ^ ^ ^ ' ' " " ' ' ~
- ^ : -
- -^
x
- ~ ~
^
important items that should continue with the exchange of data and information in the. area of erosion / corrosion.
Therefore.-it l
16 recommended that the following specific. topics be continued in
.i either existing Working Groups selected by the JCCCNRS or-i incorporated'into the proposed Working Group on aging and life i
extension that both sides have mentioned informally as a possible -
future activity:
j a)
Exchange information that identifies structural material-used in the primary loop for BWR and PWR and their performance in appropriate: operating environments.
J b)
Exchange information and explore potential cooperative efforts in diagnostic and monitoring. techniques for water chemistry and materials performance, i
c)
USSR to provide-their erosion / corrosion predictive computer code.
The U.S. make comparisons with U.S.
codes using field experience data and provide results to the USSR.
Future exchanges and cooperative efforts will be based on'the results of this comparison.
l d)
Evaluate =the Prometoi proposal' dealing with materials and components performance and reliability.
Results of this evaluation may be relevant to other JCCCNRS-Working Groups.
j e')
The Working Group recommends that careful measurements.
I
~
of corrosion products and buildup be= continued.
This will provide an understanding of the role of oxides-and i
corrosion products-(e.g., nuclides) and their transport.
I throughout the primary and secondary loops and their interrelationships to'ALARA'and corrosion performance.
f)
Investigate corroeion processes kinetics.under accident conditions.
I g)
Explore and develop joint corrosion-erosion testing of materials with the use of the USSR facilities in order I
to develop means for pipe line corrosion prevention, I
methods for lifetime and reliability diagnostics of corrosion resistanco parameters.
'h)
Exchange information on improvements in developing new j
corrosion-resistant materials for NPP pipe;11nes and equipment.
1)
Exchange specific case studies of NPP equipment materials failure.
9 w.
.-1.,
v-
..---~...--..
,, ~
.,m
-..,-.4, 5,
.s.
w
-=.n -._ a. a....
l, i
V
\\
l 1
i j)
' Exchange information on-methods for accelerated p
corrosion material structure tests, also under radiation conditions.
l' i
L k)
It is proposed that a USSR. delegation of members of Working Group 10 visit the U.S. during the fall of 1990.
The trip would include visits.at Brookhaven
]
National Laboratory, Westinghouse Electric Corporation,.
the Surry Nuclear Power Plant (PWR), the Electric-Power Research Instituto NDE Center,.the General Electric Company, Argonne National Laboratory, the Dresden Nuclear Power Plant-(BWR),-and the NRC.
Topics ofi discussion would include-prevention of erosion-corrosion, water chemistry control, NDE equipment.and techniques, and material development.
2.
The Working Group encourages tho' USSR.and the commercial q
U.S. nuclear industry to extend and continue dialogues on potential areas of cooperation and mutual benefit.. Examples-of' the potential areas of interest include a USSR in-line monitoring' device for detection of erosion-corrosion (BWRs) and the USSR corrosion product transport studier (in plant) for PWRs to 1
optimize.the water chemistry control in the secondary loop.'
- The, U.S. delegation felt it was impr.rtant that the copper ion concentration measurements be nsde at the samentime that the iron transport measurements are performed.
3.
Computer programs developed in the USSR, U.S.,
and Europe to predict pipe wall thinning due to erosion-corrosion should be compared using' actual plant experience data.
Stre.igths from each program could be used to-improve all three computer programs.
Signed in Moscow,. USSR U.S. Co-Leader USSR Co-Leader DRLs m J.
.--MTchafdson' I. A. Stepanov 10 1
a h
+
APPENDIX II List of Participants and Observers in Working Group Meetings 9
't 4
1 r
s, 4
V f
1 e
e i
=
t l:
l b
e
.s
(
0
,M f
tP=
a-
1
., _ _ _........ g---
.7,
....=
u,__,__ =,._ _
n.,, _
l WORKING GROUP 3 U.S. Particioants Co-Leader:
Shao, Lawrence C.,
Director.-Division of Engineering, Office of Nuclear Regulatory Research.U.S.
Nuclear Regulatory Commission Other
Participants:
Serpan, Charles 2. Jr... Chief Materials' Engineering Branch, Office of Nuclear Regulatory Research, USNRC Nanstad, Randy K.,
Leader, Fracture Mechanics Group Oak Ridge National Laboratory-Cheverton, Richard D.,
Section Head, Engineering Technology Division, Oak Ridge National Laboratory-Hawthorne, J. Russell, Research Metallurgist, Materials-Engineering Associates, Inc.
l-Griesbach. Timothy J.,
Project Manager, Electric Power Research Institute l
Theofanous, Theofanis G.,
Professor, University of California at Santa Barbara.
I
- e
---.-.,. 2 -?
---..mg
.s i
L
-..m____.._,_-
a, WORKING GROUP 3
- I. V. Kurchatov Inatitute of Atomie Energy: -
l Kryukov Alexander N.
Levit. Vladimir I.
Gurovitch. Doris A. -
Sokolov. Nichael A.
Krasikov. Evgenyi A.
Kevorkyan~. Yuri R.
Kapinos. Viktor G.
Tutnov, Alexandr. A.
Kiselev. Alexandr-S.
Viktorov, Viktor F.
Tursunov. = Igor - E.
Vikhrov, Viktor I.
Central Research Institute for. Structural Waterials **PROMETEY": -
Ryibin. Valeryl V.
Karzov.- Georgy1 P.
Nikolaev. Vladimir A.
Bodani n Vladimi r ' I.
Alekseenko. Nikolai N.
Ti moteev. Boris T.
Ani k ovskyi. Vladimir V.
I "HYDROPRESS":
Biryukov Gonnadyi I.
Dragunov. Yuri G.
Fil Nikolai N.
Naksimov.- Yuri M.
Rogov. Nichael F.
All-Union Research Institute for NuclearL Power Plants Operation:
Morozov Sergei K.
Getman. -. Alexander F.
Bakirov. Narat B.
USSR Academy of. Sciences:
l-Tkatchev. Vladimir V.
1 Nakhutov. Nikolay A.'
Research and Design Institute for Power -Technology:
'k Rivkin. Evgenyi Yu.
Scientific Research Institute for Heavy Machine Building:
Vishkarov. Oleg N.
Popov. Alexander A.
c-
.e
,.,,m,.
.m..
...,.m.
._.y
,.....,,,.,,.-,.~n, e
WORKING GROUP 4 1
Accendix II: List of Particioants U.S. Participants in Working Group 4: Fire Protection of. Safe Shutdown l
Capability in the U.S.S.R and the U.S.:
l Co-Leader:
Madden, Patrick M., Senior Fire Protection Engineer, Division of Systems l
Technology, Plant Systems Branch, U.S. Nuclear Regulatory Commission Other
Participants:
Kubiciki, Dennis J.,
Senior Fire Protection Engineer, U.S. Department of j
Energy Sullivan, Kenneth, Senior Electrical Engineer, Brookhaven National Laboratory U.S.S.R. Participants in Working Group 4: Firt Protection of Safe Shutdown Capability in the U.S.S.R. and the U.S.:
Co-Leader:
Mikeev, Anatoly K., Main Fire Department-Chief, Lieutenant G'eneral, U.S.S.R. Ministry of. Internal Affairs.
Other
Participants:
Working Group 4 USSR Particioants Co-Leader:
Mikeev, Anatoli K.,
Director of the Main Directorate of Fire Protection, Ministry of the Interior
,Other
Participants:
Kopilov, Nil.olai P., Deputy Director, Fire Protection Research, All Union Research bstitute Korolchenko, Alekhsandr, Ya., Deputy Director, All Union Research Institute for Fire Protection Gudkov, Alekhsandr S., Deputy Olvision Director, Main Directorate of Fire Protection Ministry of the Interior Gorelov, Alekhsandr P., Deputy Director of the Main' Directorate of GAEN Korishchenko, Nikolai D., Director of the Directorate of Fire Prevention in the Zaproozhye Oblast
Working Group 4 Zavgorodny, Vasily N., Division Director, Directorate of Fire Prevention in the Zaproozhye Oblast Nekhaev, Sergei V... Division Director, Directorate!oi-.~ ire Prevention.in i
the Zaproozhye Oblast Nazimok, Vasily I., Branch Chief, Fire Prevention, Zaporozhye NPP Bronnikov, Vladimir K., Director, Zaporozhye NPP l
Plokhy, Taras G., Chief Engineer, Zaporozhye NPP l
Grubyn, Nikolai A., Deputy Director fer Safety at the Zaporozhye NPP Sepnev, Valdimir A., Chief of Reactor Department.
Khatemkin, Vadim G., Chief of the Electrical Department Zhvk, Pavel F., Senior ~ Instructor for Fire Safety.
l Atanov, Aleksandr I., Deputy Head Engineer for Operations l
Kramchenkov, Vladimir M., Chief of Unit 1 Bilei, Danko V., Chief of Unit 4 Val'd, Evgenii M., Leader of-the Working Group of Planning (Design)'
Atakishchov, Igor G., Senior Instructor from GAEN
~
1 l
i i
)
l
. r..
. u.. _. _. _ _ _
3.,
....7-_--
i WORKING. GROUP 6 U.S.
Particioants Co-Leader:
Sheroni Brian W., Director, Division of Systems Research,:
Office of' Nuclear Regulatory Research, USNRC Other Participants
.Speis. Themistocles P., Deputy-Director for Research, Office
~
of Nuclear Regulatory Research,: USNRC -
Theofanous, Theofanis G., Professor, Department of. Chemical and Nuclear Engineering, University of California at Santa Barbara, and Director for Center for-Risk Studies and Safety' North, Paul, Manager, Nuclear Reactor Research and Technology, EG&G Idaho,-Inc.
Harper. Frederick T.,
Supervisor, Reactor Modeling and Regulatory Applications,'Sandia National Laboratories j
.+,
a
_+==.-***;e aan= +,
e4,-e*,
e e e cpe a9,. f r n p,,,,
+
+9
- =-e-
-=r
~
- )
s%
j
,i-i WORKING GROUP S l
I V.Kurchatov Institute of Atomic Energy:
i l
Asmolov. VIadimir G.
Osmatchkin. Vitalyi S.
Rueyantsev. Alexander N.
Payshuk, Vladimir A.
Budaev. Nichael A.
Tchalvanov. Boric B.
Dorofeev. Sergei B.
Shkh. O.Ya.
Elkin. Ilya V.
S1avyagin. Pavel D.
l Xobsar. Leonid L. -
- 1 Kiselev. Nikolai P.-
I Yugal. Viktor W.
Suslov Alexander I.,
Silln. Vladimir A.
Basamskyi. Evgenyi G.
Baronov. Garry S.
Degaltsev. Yuryl G.
i Shubenkov.. Andrei V.
I Netchaev. Yuryi A.
Rusanov. Vladimir D.
Pakhomov. Valoryi P Loboda. Sergei V.
Nikulshin. Vladisiv E.
Ivanov Viktor K.'
Kovalevitch.Oleg' N.
Fedul ov, Valeryl F.
Dvukhi mennyi. Viktor A.
Stepnov. Vladimir D.
Fuks. Roman'L.
Antropov..Viktor N.
Kuznetsov. Mark V.
i l
- Resorach Institute for Energy Technology:
Tcherkshov, Yuryi N.
Nikitin.-Yuryi N.
Mironov. Yuryi V.
Shi verskyi. Evgenyi A.
Polyakov. Evgenyi'F.
All-Union Research Institute for Nuclear' Power Plant Operation:
Volkov, Vyatcheslav. A.
Videneev. Evgeny1.N.
Bulynin. Valeryl D.
Pryakhin. Vladimir N.
j.
Nigmatulin. Bulat I.
q 1'
l
..m m
r... +,..
4.~.-
.~..
-. ~.
.l i
WORKING GROUP S.
"Hydropr ess":
Sorokin. Yuryi S.
Sezrukov. Yuryi A.
Logvinov. Sergel A.
Sidorov Alexander S.
Research Institute for Chemical Nashine Building:
Dulopov. Yuryi N.
Giushko. Vladimir V.
"Atonwnergoprookt" Taranov. Gennady1 S.
Shvyryaev Yuryl V.
Zvonarov. Yuryi A.
Amitchenkov. Vladimir - N.
Khasanov. Yuryl G.
V. G. Khlopin Radii Institute Galkin. Boris Ya.
Nuclear Safety Institutes Bolshov. Leonid L.
Arutyunyan. Rafael V.
Strizshov. Valeryl F.
1 Noscow Energetic Institute:
Kabanov. Leonid P.
Zemlyanukhin. Vladimir V.
Zykov. Vadim. A.,
All-Union Research Institute for Non-Organic Materials:
Butchilin. Vladisdr ' A.
i l
l
......-.1
l.j..,
__7-q
_.. = - -
.... ~..
l.
l 1
i i
WORKING GROUP 10 l
U.S. Particioants Co-Leader:
Richardson, James E.,
Director, Division of Engineering Technology, Office of-Nuclear Reactor. Regulation, USNRC j
Other
Participants:
Taboada, Alfred, Benior Materials Engineer, Office of i
Nuclear Regulatory Research, USNRC Czajkowski, Carl J.,
Research Engineer, Brookhaven National Laboratory Gordon, Gerald M.,
Manager,-Fuels and Plant Materials Technology, General Electric Company
)
Wootten, M. John, Manager, Steam Generator Technology and Engineering, Westinghouse Electric Corporation l
Wu, Paul Chu-Sheng, Metallurgist, USDOE
]
1 l
t l
i 1
.- ~ -.
- ..9.
~.u-
~ _
- y --.
l L
WORKING GROUP'10 USSR Particioants Co-Leader:
- Stepanov, I.A.,
Head of the Department, NIKIET-other Participants in Moscow:
NIKIET
- Belous, V.N., Head of the Laboratory
- Shyvalov, V.A.,
Head of the. Laboratory Ptashkin.
S.V.,
Engineer OKB "Gidrooress"
- Banyuk, G.F., Head of the Bureau
- Brykov, S.I.,
Constructor-Engineer.
NIIAR
- Toropova, V.G.,
Scientific Worker CNIIKM "Prometei" Mikhaleva,- E.I., Head of = the Sector Filimonov, G.N.',
Head of~the> Laboratory
- Timofeev, B.T.,
Head of the Laboratory Fiodorova, V.A.,
Senior Scientific Worker VNIIAM 1 '
Trubachev, V.M., Head of Laboratory Aliokhova.
I.A.,
Scientific Worker Shalobasov, I.A., Senior Scientific. Worker CNIITMash
- Popov, A.A., Head of the Laboratory NTC "Gosoromatomnadzor"
'Vasiliev, V.G..
Senior Scientific Worker-IAE
- Arkhipov, V.V.,
Senior Scientific Worker
- Ermakov, V.A.,
Senior Scientific Worker l
__n m.
e
I Working Group-10,' USSR Participants continued VNIPIET 1
- Kritsky, V.G., Head of Laboratory-Brusakov V.P.,
Head of Laboratory i
VNIIAES
- Mamet, V.A.,
Head of.the Department l
- Gashenko, V.V.,
Deputy Director.
- Huliov, Y.V.,
Scientific Worker
- Tyapkov, V.F.,
Head of the Laborecory-Gorachnin, I.N.,
Senior Scienti#ic Worker-Yurmanov, V.A.
. Head of the Group
- Erpyleva, S.P.,
Scientific Wo'*ker:
Abakumova, O.N.,
Scientific Worker Gerachnina E.B.,
Engineer i
Shirokikh, V.N.,
Scientific Worker Gerasimiuk, Y.D.,: Engineer i
- Saltanov, M.G.,
Engineer i
Nigmatulin.
B.J.,
Director Other Participants in' Leningrad:
"Prometei" l
Ignatov, Prof. Victor A.,
Deputy Director Karzov, Prof..Georgy P., Head of Department'of, Materials:for Nuclear' Energy l
Dushin, Prof. Yuriy A. -Head.of Metal ~~ Laboratory for Gas l
Reactor a
Bereshko Doc. Sci. Boris I.,' Head of Metallurgical.
I Laboratory Timofeev, Doc. Sci. Boris'T.. Head,of Laboratory ~for Strength and Reliability.
Markov,1 Doc. Sci. Vadim G., Head of. Liquid > Metal' Laboratory Zemljankin, Vladimir A., He'ad of Experimental Laboratory Poljakov Evgeniy'I.. Head of' Experimental ~ Group Anikovsky, Doc. Sci. Vladislav V.,
Expert.
Blumin, Alexander A.,
Expert 1
Fedorova,'Valentina A.,
Expert Sischikov, Alexander V.,
Expert L
Kaprizov, Vladimir A.,
Expert Ponomarov, Alexander P.,
Expert, Foreign Economic Relations Department
]
i e
q
...7......
i
..._-.-r..
1
.-l
.1 APPENDIX III-i 1
1 List'of Documents Exchanged-by the WorkingLGroups a
9 i
b b
4 l
I i
l 1
.j
.)
WORKING GROUP 3 Pacers Exchanced By U.S; Recent Studies of RPV Notch. Ductility Changes with Postirradiation Annealing and Reirradiation.
J.R. Hawthorne, Materials Engineering Associates, Inc..
Regulatory Guide AXX (Draft) Form and Content of Safety-Analyses for Annealing of a Reactor Vessel-Beltline.
]
P.N.Randal1, A.Taboada, and C.Z.Serpan, -Jr., USNRC Embrittlement of.the Shippingport Reactor Neutron Shield Tank.
O.K.Chopra and W.J. Shack..Argonne National Laboratory. and S.T.Rosinski, Sandia National Laboratory i
)
Effects of Irradiation on Crack Arrest Toughnesslof 4
Submerged Arc Welds and Stainless Steel Weld Cladding.
Overlay.
R.K.Nanstad, S.K.Iskander, F.M.Haggag, and W.R.Corwin, Oak-Ridge National Laboratory.
Experimental. Fluence Rate Studies.
J.R. Hawthorne, Materials-Engineering Associates, Inc.
An overview of Radiation Embrittlement Modeling for Reactor Vessel Steels.
T.J.Griesbach, Electric Power Research Institute Irradiation' Embrittlement of Reactor Pressure Vessel Steels, j
G.R.Odette, University of California, Santa Barbara-A~Probabilistic Approach to the Evaluation of the PT8' Issue.
R.D.Cheverton, Oak Ridge National Laboratory 1
The USNRC/ORNL Integrated Pressurized Thermal Shock Analysis and Methodology.
R.D.Cheverton, Oek Ridge National Laboratory Physically Based Regression Correlations of Embrittlement Data from Reactor Pressure Vessel Surveillance Programs'.-
Fracture Control Corporation and' University of. California at.
Santa Barbara, January 1984, EPRI NP-3319 Irradiation Embrittlement of LWR Pressure. Vessel Steels.
University of California at' Santa Barbara, January 1989.
EPRI NP-6114 Thermal Annealing'of an Embrittled Reactor Vessel, Feasibility and Methodology.
Westinghouse Electric Corporation. January 1989 EPRI NP-6113-SD j
~....
l Working Group-3 Page two Estimating Fracture Toughness Using Tension:or Ball l
Indentation Tests'and a Modified critical Strain Model, PVP-Vol. 130, Innovative Anoroaches~to Irradiation Damano
{
and Fracture Analysis; Editors: D.L.Marriott, T.R.Mager,-and W.H.Bamford,-Book No. H00485, 1989.
F.M.Haggag and R.K.Nanstad, ORNL-I Structural Integrity Evaluation Based on an Innovative Field Indentation Microprobe PVP-Vol. 130, Innovative Anoroachesc j
to Irradiation Damane and Fracture Analysis; Editors:
D.L.Marriott, T.R.Mager, and:W.H.Bamford, Book No. H00485,
)
1989.
I F.M.Haggag and R.K.Nanstad, CRNL j
Tensile and Charpy Impact Behavior for Irradiated Three-Wire i
Series-Arc Stainless Steel Cladding, Effects of Radiation on 1
Materials; 14th International Symposium.(Yol. II). ASTM i
STP 1046, Editors: N.H.Parban, R'E. Stoller, and A.S.Kumar, American Society for Testing and Materials,. Philadelphia,'
1990, pp. 361-372.-
F.M.Haggag, W.R.Corwin, D.J. Alexander, and R.K.Nanstad.10RNL l
Effects of' Radiation on N. Curves for'Hish Copper Welds, Effects of Radiation on Materials; 14th-International Symposium (Vol. II). ASTM STP 1046 Editors: N.H.Parban,
+
R.E. Stoller, and A.S.Kumar, American Society for Testing and Materials,-Phi'adelphia, 1990, pp. 361-372.~
l R.K.Nanstad, D.C.McCabe, B.H.Menke, S.K.Iskander, and I
F.M.Haggag, ORNL i
Irradiation Effects on Thermal Conductivity of:a Light-Water Reactor Pressure Vessel Steel; Journal: of Nuclear Materials, Volume 115, Nos. 2 and 3, April 1983, Amsterdam.
R.K. Williams, R.K.Nanstad, R.S. Graves, and'R.G.Berggren, ORNL l
Fracture Toughness; Pressure Vessel and Piping Technology l
1985--A' Decade of Progress; Editor: C.(Raj)Sundarajan, American Society of Mechanical Engineers, 1985 R.K.Nanstad and D.P.Edmonds,'ORNL
. l.J "
- =
- ' : = :- - - --
-~ - - - -
~ ' ~
l Z ZU-" ]
i Working Group-3 Page three i
1 WORKING GROUP 3 By USSR Scientific-Engineering and Working Plans to Conduct Annealing y
of the VVER-440 Type Reactor Vessel and the Experience Gained i
From 'Ihese oporatton.
A.D. Anaev. -Institute of Atomic Energy N.F.Rogov. "Hydropresa" Determination of Radiation Embrittlement'of Vessel hterials j
Af ter Annealing as a Basis for Operation.
J A. D. Anaev. ' A. N. Kryukov. M. A. Sokolov.. Institute of. Atomic Energy j
Research on Reactor Vessel hterials Fron Decommissioned Reactors.
Resistance to Vessel Naterials Fracture..
V.V. Robin. A.N.Nikolaev. A.N.Norozov. 1..A.Vainor. Centra 1
?
Research Institute for Structural Natorials "Prometey" C CRISNP)
~
i Peculiarities of the Vessel' Structural State.
V. V. Ryubin. CRISNP Annealing Radiation Damage in Vessel Natorials.
Yu. A. Ignatov. V. A. Nikolaev. V. J. Badanin. ~ CRISNP.
Microanalytic Research of Natorials Under Neiting Point in i
Different Strata of the Vessel.
l A. N. Ammev. E. A. Krasikov. A. V. Novikov. A. J. Biryukov. InsLitute of Atomic Energy i
Radiation Embrittlement of VVER-iOOO Reactor, Vessel Materials Irradiated in Research Reactors.
l l
-A.D.Ammev. A.H.Kryukov, V. I. Levit,. N. A. Sokolov. ' Insti tute of Atomic Energy t
Radiation Embrittlement of Natorials Irradiated in Experimental Research Reactor.
O.N.Vichkarev. Yu. I. Zvezdin. NPO.CNII*IMA91 '
Anslysis and Summary of-Results on Research of Radiation Embrittlement of VYER-440 Vessel' Natorials on Surveillance Specimens.
A. D. Amaev A. N. Kryukov. V. I. Levit. P. A. Platonov N. A. Sokolov.
Institute of Atomic Energy Technical Neans and Assessment Results of Radiation j
Embrittlement of : Reactor Vessel Materials in Operation Con the Basis of Determination of Diagram Impression).
N. B. Bakirov, VNII AES E
e
-,w---
+
,.,,-v
. m.
.._,.,_,.m.
.m..
.. +.., ~. - -. - -
v,,
-.,, ~......, _, ~,.
.~
Working.~ Group.3 Pago four 1
WORKING GROUP 3 The Issues of the Modeling Processes 'of Radiation Embrittlement of Waterials of the Vessel.
J. R. Kevorkyan. Institute of Atomic Energy.
Research of.the Microstructure and Nochanissa of Radiation Embrittlement of Natorials of the; Vessel.
B. A. Gurovitch. Institute of Atomic Energy -
The Influence of Fast' Neutron Flux Density.on Forming,
Nieropores in Alpha-Iron Low Flux Zone CInvestigation of the Nethods of Small Angle X-Ray Scattering).
L. Yu. Nogilevski. USSR Academy of Sciences.'
'/ G. Kapinos. P. A.Platonov D.I. Svergun. Institute of Atomic j
Energy:
. i Thermohydraulies and Accident Scenarios for Analysis, - of
(
Thermal Shock Under Pressuro.
N. S. Fil. "Hydropross" Basi'c Principles and Directions of - USSR Studies. on Demonstration of Strength Ctoughness) of VVER vessels.
G. P. Karsov CRISNP Nethodologies for VVER Reactor Vessel Evaluating at. the Time of hermal Shock.
G. P. Karsov, V. A. Petrov. B. T. Timoreev. CRIBNP.
V. V. Oshigin. NPO CKTI.
E. Y. Revkin. NIKIET Analysis of Neasurements to Guarantee' Resistance to Brittle 5
Failure of the VVER-440 Reactor ' Vessel at the Time 00 Thermal Shock.
O. I. Biryukov Y. G. Dragunov. A. N. Ivanov. Yu. N. Naksimov.
"Hydroress" 3
Comparison and Analysis,of Calculational Results on
}
Probability of Failure of the Vessel HBR-HYPO During-Accidents with hermal Shock Using USSR and USA Code Calculations.
A. A. Tutnov, Institute of. Atomic Energy.
TJ. B. Tkatchev. GPAN USSR Probability Aspects 'of the Results of -VVER-1000 and VVER-440 Vessels Resources Evaluation A. A. Tutnov. Institute of: Atomic Energy.
V. V. Tkatchev. GPAN USSR i
.,e
.n,,,
n,.
n,
...,,r,
,-r,-,e a a
-n. v -,,..
n-
.u~
,m
. - -..,,... +,,. -,,., ~.,...
.e
-. - -. ~
l
.~
Working Group 3
-i Page five WORKING GROUP 3 Experience in Fracture Nechanics Calculations of Design -
Elements at the Time of Verification of Standard Engineering Dependence.
A. A.Tutnov A.S. Kiselev. A.Yu Sergeev Institute of Atomie Energy..
V. V. Tkatchev.. GPAN USSR Verification of 2-D and.3-D Algorithms of Elastic-Plastic Calculation of Tension-Deformed State of VVER-type Reactor 1
Vessel Under lhermal Conditions.
- A. A. Tutnov, A. S. K1selev. A. P. Kasatchkin. Institute of Atomie
- Energy, V. V. 'Deatchev. GPAN USSR s
e 4
' % en,
G 9
F re----,-
,-r e-.-
, e ew----
w,->-4
- --- - --,.- -.,e-
-- w
,-,=--,r-.
t-
?1 Working Group 4 Accendix III:
Documents Exchanged by Working Group 4:
By U.S.:
NRC Inspection Procedure 64100, Postfire Safe Shutdown, Emergency Lighting and Oil Collection Capability at Operating and Near-Term Operating Reactor Facilities, Issued Date: 3/16/87.
NRC Inspection Procedure 64150, Triennial Postfire Safe Shutdown Capability Reverification, Issued Date:'3/16/87.
NRC Inspection Procedure 64704, Fire Protection / Prevention Program, Issue Date: 2/12/86.
j NUREG-0800, NRC Standard Review Plan, 9.5.1 Fire Protection. Program, Rev. 3 - July 1981 TR-A-3720-1, Inspection' Techniques For Post-Fire Safe Shutdown of Nuclear Generat hg Stations, Rev. O, January 1989, Prepared by Brookhaven National Laboratory for the U.S. Nuclear ' Regulatory _
Commission, i
By U.S.S.R.:
Scientific and Technical Results, Fire Protection, Vol. II Moscow 1990 Ministry of Atomic Energy of the U.S.S.R, Fire Prevention Standards, in the planning (designs) of atomic stations [ Station Safety Norms 01-87), Smolensk,1988 W
4
.s WORKItG GROUP 6 By the U.S.
Assessment of Candidate Accident Management Strate 91es, NUREG-5474 (March 1990)
Accident Management Information Needs, NUREG/CR-5513, Volumes 1 and 2 (April 1P90)
A Systematic Process for Developing and Assessing Accident Management Plans, NUREG/CR-5543 (March 1990)
Reactivity Accidents, NUREG/CR-5366 (January 1990)
Severe Accident Ins 19 hts Report, NUREG/CR-6132, April 1988 Individual Plant Examination Submittal Guidance NUREG-1335, August 1989 Individual Plant Exsmination Generic Letter Provided to U.S.
Industry, USNRC 88-20 i
i i
i I
i 9
e
~
I' Working Group 6 Page two 4
MKING GROUP S By USSR 06 sop npor
, B.Acmonos,pavuW mCCaemosaHMa taaeaWx asapMa na ABC a CCCP.
MAS mm.M.B.MypwaTosa 3xCnopMueHTambHue uCCasaosaHMa a momenMposaHMe npoueCCon nepenemeHMm $poHTa ropeHMR somoposa a nopeMoam me$4arpauMM e aeToHauMe, sWCoxoTounepatypHot CamosoCnnameneHMe somopoma.
B.9aammHos, MA3 mm. M.B.RypgaTosa 3xCnopMueHTambHWe mCCaoaosaHMR m momeaMpos&MMJ npouscun pmCnpoCTpaHoHMn somopoma. W.Byames, MA3 mm.M.B.Mypgatosa DCo6eHHoCTM @MSMMo-MMmMMeCxMK momeasA npoueCCom o6pa90amHMR sonoposa npH rMnoTeTMweCxMn anapMax m TenHMwoCMMe CpeacTsa aan ynpasaeHMm MoHueHTMEMeA somopoma.
B.naxonos, MA3 mm.M.B.RypgaTosa Coo 6aeHMe cose?CxMM CneuManMCTom o SxCnepMueHTanbHWM CTeHamM, naaHMpyeuWK onWTaM M pm6otaX no sepM$MuauMM pmCMOTHWK Monom a xawecTse exaaam a nporpaumy ICAP.
MHTerpanbHam FCTaHoaxa I*IF-WER.
M.EAxMH, MAS Mu.M.B.RypgaTosa Tenao@MoMMecxMR CTeHa RC.
A.Mo6sape, MAS Mu.M.B.MypwaToma RooposMoHHWe, somonMuM9eCxMe CTeHaW.
B."ameMuo, SHMC CToHAW no McCnemonaHMO TRReaWM maapMR.
B.BynWHHH, BHHHA3C PacweTHWo MCCacaoskHMM.
X.ConneHuos, BHHMASC 06 sop nporpamu vennormapasaMweCxMx mCCaemosmHMa a CCCP.
B.HMrumTynMH, 3HHC 0 noHMuaHMM a MmCTopast speum npo6AouW mamMuomeRCTsMR pmCnnana axTMsHoA soHW C 6eToHou M sonoR (MnDMenWo
@MoMxo-xMuMwoCxMe maneHHR, nocnemostTOabHoCTb BBaMuomeACTsMA, npMouneuwe pacMeTHWe momenM.
P.ApyTOHmH, MEPAS AH CCCP BWooaW ma aHaaMoon vaneaWx anapMa a sepomTHoCTHWx ouenox pMCxe (exCnepMueHTaabHWe, RHanMTM4eCxMe MporpaMMWI ofHoCMTenbHo 6yayaMK pa6of (DxCnepMueHTanbHWK, aHanMTMweCxMx 1.
~
A.Bonbmos, MBPA3 AH CCCP 4
I Working Group 6 Page three l
l
'.i wokKINS GROUP e l
l O wowuenuMu ynpasaeHun-vameAuuu anapumuu Ma ASC a CCCP.
1 0.EmM, MAS um. M.B.Mypwatosa OCnameHMS peaMTopa B-1000 oncremoR naoCNsHol'o OTsoAm *tenna xmx enoCo6 nonWaeHNm 6esonaCHoCTM N eMMaeHMS DepoRTHoCTM i
TasenoR asapMM.
1 r.Tapanos, ArosswepronpoenT j
O ownsowan noTeMuMaAbHoro PMCMa TmasAWM paaMauMoMHWM 4
1 nocneAeTsMR npu mCnonmsosawnu enCreu e6poca mannoHun m l
gunwTpaunx sW6poca as smaMTHoR o6oMo4NN A3C.
n.CassarMH, MAS wu.M.B.MypwmTosa j
MotoAW aHaMMBa NHuMASMToo Ma ASC.
l B..OCuawxMM, MAS um.M,.B.Mypgarosa l
BepoMTHoCTHWe aHaMMS MpoeMTMoR 6esonacMoCTM pomMTopHoR FCTaHoenn BB3P-1000.
A.PyuMHues, MAS um. M.B.MypumTosa j
l BesoRTHoCTHWR aHaMMS 695onaCHoCTM ASC C peaMTopou BB3P-1000.
O.Itsupmes, ATousHepronpoonT t
J i
J
\\
)
' I
):
I i
e l
e
m,_....
I i
WORKING GROUP 10 l
Pacers Exchanned By the U.S.
)
4 Qualification and Use of Type-316 Nuclear Grade Stainlest, 1
Steel in Boiling Water Reactors.
G.M.Gordon, General Electric Company l
Improvement in Composition and Control of Water Chemist.ry in BWRs.
1 G.M.Gordon, General Electric Company BWR Corrosion Product Transport and Radiation Buildup.
G.M.Gordon, General Electric Company Chemistry Control in PWR Nuclear Plants in the USA.
M.J.Wootten, Westinghouse Electric Corporation i
Corrosion Product Transport in PWR Plants in the USA.
i M.J.Wootten, Westinghouse Electric Corporation
{
Ultrasonic Testing of Piping for Stress Corrosion Cracks.
I A.Taboada USNRC The Use of Alternate Materials for Hitigating i
Erosion-Corrosion.
A,Tatoada, USNRC Boric Acid Attack of Reactor Components.
C.J.Cza,ikowski, Brookhaven National Laboratory I
Nondestructive Inspection for Detection of Erosion-Corrosion.
C.J.Czajkowski, Brookhavet. National La'> oratory-i I
1 I
l l
y
,,_,,d.k
_,,y_,y.r--..'
~,
A r
x:--
~- :-
- i..
w.;
w-o.
Wdrking Group 10 i
Page two The USSR Reports on JCCCNRS Workins Groop 10 Conference Monday 25 June. 1990 1.
Stepanov I.A. NIKIET 1he main directions'in develop-ment of the NPP's corrosion state control systems in the USSR.
2.
Bryhov S. I.. Banruh G. F.. Titov V. F. OKB *GidroPress" On damase of heat exchanger tubes in steam senerators a
at NPS with WVER.
1 3.
Isnatov V. A.. Timofeev B. T., Karzov G. P.. Fedorova V. A.
CNIIKM "Promete1" Corrosion-mechanical strensth for NPP materials.
4.
Kritsky V.G..
StYa2schhin P.S. VNIPIET On tendency l
of cooline water to hardness salts ' segregation on heat transfer surface.
5.
F111PPov G.A..
Martynova S.I.. Saltanov G.A..
Kuhush-Kin A.N.
VNIIAM Protection of NPP Power equ1Pment and P1Pe-lines from corrosion-erosion wear with the help of octadeCylamine,microaddit1Ves.
Tuesday June 26. 1990 (Electro 80rsh) 1.
Niematulin B.I..
Saltanov M.G.
YNIIAES Numerical simulation of threshold and transition Processes in e
" steel - flowing heat-transfer asent" system.
Numerical simulation of erosion-corrosion wear (ECW).
e.-
c.
v
,,--.y
- - - -. - + - -.
W rking Group 10 j
Pigo throa 2.
Jurmanov V.A.. Sovetnikov K.V..
Kot1ov V.Ya.. Trap-Mov V.F..
ErPyleva S.F.
VNIIAES Investigation of corrosion firmness of various structural steels in HPP condensate-feed line with PWR, 3.
Eudryavtsey B.E.. Tr4Khtenbers 1.. I.
VNIIAES i
VNIIAES eKPerlence of workins in non-destructivt control field durins NPP operation.
.4.
Bykova V.V..
ErPyleva S.F..
Mamet V.A..
Traphov V.F.
VNIIAES Corrosion Products distribution in air-steam circuit of Power unit with PWR-1000 under hyd-ra21ne water condition.
Wednesday June 27, 1990 1.
Lysikov B.V.. Strelhov B.P. HIKIET Equipment and P1Pe-l lines diagnostics system in BWRs.
i 2.
Kritsky V.G..
Dementiev A.V., Sofin M.V..
Shults V.A.
VNIFIET Polarization resistance method for steel corrosion rate measurements in water heat-transfer agent of NPP.
3.
Trubachev V.M..-
Nazarov C.I..-
Antoshkin N.M..
S1-l lin A.V..
Semenova S.P.
VNIIAM ComParat1Ve erosion-corrosion investigation of steels of different classes
.in flows of wet steam.
l 4.
F111PPov G.A.. Nov1Mov I.I..
MorduKhovich A.M., Shalo-basov I.A.
VNIIAM New method of improvement in ero-slon resistance of steels applied in Power ensinkering industry.
r
~.
Wo'rking Group 10 Page four 5.
Tutnov A.A.. Serseeva L.V.
IAE Zirconium P1 Pes nodular corrosion of Passage reactors.
I i
6.
Brus&Kov V.P.
VNIFIET SCC under thermodynamic forces l
action.
Thursday June 28. 1990 l
1.
Zve2 din Ju. I.. Kuznetsov E. V.. Iharina I. L.. ~ Gerasi-f mov V.I. CHIITMash Corrosion cracking of low-alloyed steels in high Parameter water.
2.
Borisov V. P., Kuznetsov E. V.. Gerasincy V. I.. Khari-na I.L.. Sandler H.G.
CHIITMash Corrosion-resistant steels for P1Pe systems of heat-exchanser equ1Pment.
l Friday June 29. 1990 f
1.
Chabah A.F.
IAE Peculiarities of heat-tralasfer l
i e
e 1
=
l
\\
l i
L f
l
[
1 s
l Working Group 10
]
Page five i
i
]
WDRKING GROUP 10 Additional Pacera Exchanced By the USSR Experimental Investigation of SAR Effect on Energetic Frosion and Acoustic Characteristic of Power Equipment.
2.A.Shaobasov, A.N.Kukushkin V.A.Michailov, Nuclear Power Research and Development Institute, Moscow
)
t Use of Surfactant Microadditives.
Prof.G.A.Saltanov, VNIIAM y
Control of Erosive-Corrosive Wear of Power Generating Equipment with Microadditives of Surfacants.
A.Kukushkin, O.Povarov, I.Shalobasov, A.Derendovsky, V.Mikhailov, V.Rastorguev, G.Tomarov, VNIIAM and MEI Untitled Paper describing Activities at Electrogorsk.
System of Models and Instrumentation for Solution of Erosion-Corrosion Problems.
New Method for Increase of Erosion Resistance of Structural Steels Used in Power-Plant Engineering, i
G.A.Filippov, J.J.Novikov, A.M.Mordukhovidch, J.A.Shalobasov Nodular Corrosion of Channel-Type Reactor Zirconium Tubes.
[
V.S.Karasey, V.G.Kovyrshin V.V.Kolesov, L.V.Sergeeva, A.A.Tutnov, L.I.Chirko, A.A.Shinakov New Equipment and Procedures for Erosion-Corrosion Tests of Power Unit Materials LL Steam Power, Nuclear Power and Hydroelectric Plar.ts.
Calculated Pa;-ameters for Operational Evaluation of Water Chemistry in the Primary Loop of Reactor Type VVER-1000.
G.I.Gorysainova, V.G.Kritsky, P.S.Styazhkin Corrosion Product Distribution in the Water Steam Loop of VVER-1000 Units with a Hydrazine Water Regime.
l V.V.Bykova, S.P.Erplyleva, V.A.Mamet, V.F.Tyapkov i
l Using Polarization Resistance to Measure the Rate of Steel l
Corrosion in Nuclear Power Plant Water Coolants (Booklet).
l V.G.Kritsky, A.V.Dementev, M.V.Sofin, V.A.Shultz, VNIPIET Research in Chemistry, Technology and Radioactive Materials Applications (Booklet) Leningrad, 1981, " Formation and Deposition of Corrosion Products in Atomic Energy Unit Loops Under the Influence of Galvanic and Thermoelectromotive Forces."
V.N.Brusakov, et al.
7 m..
,, _, - - ~~. - - -. _. -.
_,,,..--r
- -**?L.
3,
.... ~.. -_
i Working Group 10 i'
Page six l
l Working Group 10. Additional USSR Papers continued l
Research in Chemistry. Technology and Radioactive Materials Applications (Booklet) Leningrade 1979, 0n Metal l
Hydrogenation in Heater Surfaces of Energy Units."
V.P.Brusakov, et al.
1 Mass Transferred Model During Boiling Coolant Radiolysis.
V.V.Arkhipov, et al.
Listing of Offers on Scientific-Technical Cooperation Between Central Research Institute of Structural Materials "Prometei" and Scientific-Research Organizations and Laboratories of the USA.
On Damage of Heat Exchange Tubes in Steam Generators at NPS 0
with VVER.
V.F.Titnov, G.F.Banyuk, S.I.Brykov, OKB "Gidropress" Booklet on the Work of "Gidropress" Research and Development Bureau (RYDB).
The Main Directions of Work to Control NPP Equipment Corrosion State.
I.A.Stepanov, RDIPE I
i l
I I
-_..c,..
~,.. ~
b i
p J
P a
e F
l i
t Workir.g Group 3 Trip Report I
I i
f I
f i
v t
(
l i
1 l
h i
l
+
i i
l l
i h
s---
. ~. _ _,.. -
.,.,.. _...