ML20024H346
| ML20024H346 | |
| Person / Time | |
|---|---|
| Issue date: | 05/02/1991 |
| From: | Taylor J NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | NRC COMMISSION (OCM) |
| References | |
| SECY-91-119, NUDOCS 9106030036 | |
| Download: ML20024H346 (28) | |
Text
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POLICY ISSUE (Information)
May 2, 1991 SECY-91-119 For:
The Commissioners Fromt James M. Taylor Executive Director for Operations Sub_iect :
RESULTS OF U.S. DELEGATION REVIEW 0F USSR RESEARCH CAPABILITIES ASSOCIATED WITH PASSIVE PLANTS AND RELATED AREAS
Purpose:
To inform the Commission of the results of the recent visit of the U.S. Delegation to U.S.S.R. research facilities and the staff's intentions to pursue cooperative research with the U.S.S.R. in several areas of NRC interest.
Backaround:
Under the auspicies of the U.S./U.S.S.R. Joint Coordinating Committee for Civilian Nuclear Reactor Safety (JCCCNRS) by letter dated December 21, 1990, N. N. Ponomarev-Stepnoy, First Deputy Director, Kurchatov Institute, set forth several passive plant research areas which he believed may be of interest to the NRC and U.S. Industry.
He also invited a delegation from the U.S. to visit +.he Soviet experimental facilities and institutes.
The invitation was subsequently affirmed by Victor Siderenko, First Deputy Minister, Ministry of Nuclear Fower and Industry.
Mr. 'aiderenko is the current Soviet Co-Chairman of the JCCCNRS.
CONTACT:
NOTE:
TO BE MADE PUBLICLY AVAILABLE B. Sheron, RES IN 10 WORKING DAYS FROM Tile 49-23500 DATE or THIS PAFER 9106030036 910502
The Commissioners <
Discussion:
During the period April 19-27, 1991, Jim Sniczek headed a U.S. delegation to the Soviet Union for the purpose of developing a better understanding of the U.S.S.R. research capabilities in the general areas of evolutionary and passive plants.
In addition, the delegation was tasked to determine the feasibility of the Soviets conducting selected research on a cooperative or commercial basis.
The U.S. delegation included NRC, DOE, EPRI, and Westinghouse representatives. As discussed in the enclosed Memorandum of Meeting, the U.S. delegation was favorably impressed with the capabilities of the various Soviet institutions.
The U.S. delegation listened to many presentations on a wide variety of ongoing or planned research programs in the U.S.S.R.
Based on these presentations, the staff has determined there are several programs of interest to the NRC and our cooperative participation would be of overall benefit to the NRC.
These areas are as follows:
1.
Hydrogen Research - The Soviets described several facilities of various scales they are using or plan to use to investigate hydrogen distribution in containments.
Although the NRC has in the past participated in hydrogen distribution experiments (i.e., HOR facility in FRG), the NRC currently does not have any programs to experimentally examine hydrogen distribution in containment.
In addition, participation in this program would provide unique validation data for our computer codes.
The Soviets also have substantial expertise in the area of hydrogen burning and detonation.
The staff also believes a worthwhile cooper ative program would be to provide the U.S.S.R. with the NRC's HMS code for calculating hydrogen burning and detonation, and request them to independently assess and validate it as appropriate against relevant available Soviet data.
2.
Thermal Mixina in Vessel Downsomers - The Soviets showed the delegation data they obtained from one quarter scale experiments in which the mixing of cold, injected ECCS water with the warmer water in the downtomer region was studied.
This facility is of potential interest to the NRC for running mixing experiments prototypic to U.S. plants.
The NRC currently has no experimental research in the area of downtomer thermal mixing and this data would add to
The Commissioners i' our existing data base for pressurized thermal shock analysis as well as provide unique data at a different scale.
However, further discussions to ascertain adequacy of instrumentation, and prototypical comparisons to U.S. plants are needed before a definite commitment could be made.
3.
Vessel Integrity Durina Severe Accidents - The Soviets discussed several planned experiments to investigate the behavior of the vessel lower head when subjected to contact with molten core materials during the core relocation portion of severe accidents, in one experiment, proposed to be run at Obninsk, molten core material will be poured into a scaled lower vessel head.
In a second experiment to be performed at Podolsk, the Soviets will simulate a section of the lower vessel head, and electrically heat it in order to experimentally determine the dryout heat flux when the outer surface of the vessel lower head is submerged in water.
The only tests we currently are performing are at the Joint Research Center, ispra, Italy and involve pouring corium melt into water.
Both of the Soviet tests will provide potentially valuable data regarding the likelihood and possibly the mode of lower head f ailure under severe accident conditions with and without a flooded lower cavity.
The staff believes the most effective way to implement this cooperative research is through a bilateral cooperative research agreement between the NRC and the Kurchatov Institute.
The Division of Systems Research in the Office of Nuclear Regulatory Research will coord;nate and carry out this cooperative agreement for the NRC.
The JCCCNRS will also oversee and coordinate as necessary this cooperative effort.
Although the Soviet research is being conducted by a number of institutions, we have requested and obtained the agreement of V. Sidorenko, First Deputy Minister, that all cooperative research will be coordinated by the Kurchatov Institute for the U.S.S.R.
As is stated in the Memorandum of the Meeting, the U.S. will draf t a bilateral cooperative agreement detailing the work we expect the Soviets to perform, along with a schedule for performance, and forward it to them for review.
Ve currently anticipate that the NRC contribution will be on the order of $250,000-1300,000.
From informal discussions with out Soviet counterparts, we currently estimate the cost of a technical staff year in the Soviet Union to be on the order of 530,000-$50,000 per year.
However, we cannot at this time accurately estimate the costs of conducting experiments.
It is our intention to estimate the Soviet staff-years necessary to carry out the
- _ ~ - -. -
The Commissioners research proposed by the U.S., and to allocate a reasonable amount for testing costs.
If our estimates are not acceptable, we expect the Soviets will notify us to this effect upon their review of the draft agreement.
Negatiations would then be necessary to resolve differences.
This type of cooperative arrangement, in which the NRC financially contributes to a foreign program in return for scientific information, is not new.
In addition to numerous previous programs, current programs of this type include our participation in the French "Phebus" program and the large scale melt-water interaction tests being run by the Commission of European Communities at the Joint Research Center in Ispra, Italy.
However, due to the newness of our cooperation with the Soviets, and our general lack of actual experience regarding their ability to perform research that meets our needs on schedule and within agreed upon costs, we will have to carefully monitor this program. We will keep the Commission informed of our degree of success with this cooperative program.
Finally, we expect the U.S. -industry to carefully monitor the degree of success with this cooperative program in order to determine if and to what extent they would consider placing commercial work at Soviet institutions. The Soviets l
were made aware of this and we anticipate this will provide an added incentive for them to perform well, The staff is in the process of preparing a more detailed report of the visit.
I expect to be able to provide it to the Commission for information in about two-three weeks.
/
ff/L JmesM.Thkor l
xecutive Director l
I for Operations
Enclosure:
Memorandum of Meeting DI bT RIBUTIO.N :
Concissioners l
1*
HEMORANDUM OF HEETING FOR REVIEW OF USSR RESEARCH ON PASSIVE DESIGNS April 22-26, 1991 in the USSR States delegation was invited to review USSR research The United reactor plant design and tour research laboratories and on passive test facilities in the USSR.
The U.S.
side was represented by government and industry personnel responsible for
- research, engineering, and licensing of advanced reactor plants, including these employing natural circulation principles.
The meeting took Obninsk, Nizhny Novgorod and at various locations in Moscow, place Podolsk during the period April 22-26, 1991.
1 The U.S.
delegation was headed by James H.
- Sniezek, Deputy Executive Director for Nuclear Reactor Regulation, Regional Operations and
- Research, United States Nuclear Regulatory Commission.
The USSR delegation was headed by V.
A.
Sidorenko, 5
First Deputy
- Hinster, USSR Hinistry for Nuclear Power and
- Industry, assisted by N.N.
Ponomarev-Stepnoy, First Deputy Director of the Kurchatov Institute. In preparation for the visit, the U.S. side proposed discussion topics and questions which are included as an Appendix. The delegation visited the sites listed below and held discussions as follows:
I.V.Kurchatov Atomic Energy Institute (KAEI), Hoscow On Apri.1 20, 1991, Kurchatov officials presented documents to the delegation covering the week's presentations.
V.
A.
Sidorenko and N.N.
Ponomarev-Stepnoy met with James H.
Sniezek and-the members of the delegation on April 22, 1991 to discuss the overall agenda for the visit and to emphasize the importance of the ongoing cooperative effort between the U.S.
and the USSR.
Following introductory
- remarks, the delegation participated in technical discussions concerning studies of the natural circulation process under various operating conditions, and hydrodynamic stability studies. The presentations included:
1.
KC Thermal-Physical Rig (including the AST-500 model).
2.
Di: tit rovg rad Experimental Facilities, including the SM-2 and the VK-50.
1 ETO C5UPE
4 3.
Kurchatov studies on the VK-50, including information on the stratification of two-phased flows in the common riser with analytical model verification and parameters of steam entrapment into the downcomer of the natural circulation loop and safety improvements.
4.
Work by the Central Design Institute of Leningrad on their test facilities, including the large steam / water test facility at the Central Boiler and Turbine Institute and on experiments with thermal shock.
5.
Work by Polzunov Central Boiler and Turbine Institute on seismic and vibration isolation, specifically by the CKTI Damper.
6.
Work by Electrogorsk on the Integral Test
- Facility, including investigation of thermo-hydraulic problems.
7.
Work by Kurchatov Institute on the GAMMA thermo-electric
- facility, the prototype of independent unattended energy sources of small power level.
B.
Modeling of and experiments on hydrogen burning and detonation.
9.
Electro-chemical methods for measuring hydrogen concentration and pH in the coolant of LWRs.
- 10. Stability of thermal-hydraulic and neutron physics parameters, including VK-50 stability boundaries.
- 11. Future experiments on uranium-d~ioxide melt progression on the reactor vessel.
l The delegation then toured the " GAMMA" Reactor Facility, where presentations were made on small nuclear plants to produce heat I
and electricity and on noise and oscillator experiments, and the l
"KC" Thermephysical rig with subsequent exchange of viewpoints and summation of preliminary results of the joint activities.
l The Institute of physics and Power Engineering (FEI), Obninsk f
A tour of the test facilities and discussion of experiments was i
conducted on April 23, 1991.
P.L.
- Kirillov, Director of the Thermophysics Department, led the day's presentations at Obninsk.
Technical discussions were held with the scientists and engineers I
at the Obninsk facility describing their efforts and considerable f
achievements in the development of reactors and experimental and theoretical research in thermal hydraulics. These included:
i
- 1. Investigations of natural and forced circulation 2
- 2. Studies of flow structure using thermal and acoustic sensors
- 3. Hydrodynamic stability experiments for the channel as well as the entire test loop, including the stratification of the coolant 4.
Hydrogen distribution in containment and the effects of sprinkling, including the development of a computational model
- 5. Planned experiments on the interaction of corium with coolant and experiments conducted using models
- 6. Fundamental and applico experiments using the liquid metal test rig i
- 7. Construction of a high and low pressure hydrodynamic test facility i
l i
Nizhny Novgorod Nuclear District Heating plant and Experimental Machine Building Design Bureau (OKBM), Nizhny Novgorod i
The U.S. delegation traveled to Nizhny Novgorod on April 23, 1991 to participate in discussions on April 24, 1991, regarding the nuclear heating plant and the Experimental Hachine Building Design Bureau analysis and experimental capabilities in the field of heat l
transfer, natural circulation, hyr' rody nam i c o and valves and pumps l
for PWRs.
The information presented by the USSR side which was I
headed by F.M. Mitenkov, General Designer, OKBM Director, should l
prove helpful in evaluating the passive reactor designs in the U.S. The visit to Machine Building Design Bureau's experimental facilities represented the first time an American delegation has visited these installations.
l The tour of the special thermal physical rigs, used to study natural circulation stability and the nuclear district heating plant installation, were of noteworthy assistance in understanding the USSR research and significant accomplishments in this area.
The Experimental Machine Building Design Bureau presented l_
discussions relating to heat transfer and fluid flow under natural I
circulation, heat transfer in the presence of non-condensibles, mixing in a two phase fluid flow medium, information on isolation and safety
- valves, and recirculation pump seals.
Specific i
presentations included:
1.
OEPM activities 2.
Integral reactor model for thermohydraulics study under normal and accident conditions (Test Rig 1385) 3.
Study of thermophysics and transients in the integral nuclear reactors with built-in pressurizer (Test Rig L-880).
l l
3
heat Thermohydraulic studies of the vertical section tyto 4.
exchanger model.
I 5
NPP reactor coolant pumps.
6.
Hydrodynamic seair of the NPP reactor coolant pumps.
7.
Valves for the NPP.
8.
OKBM Experimental Base (Test Rigs _1312, 940 L-186, etc.).
Experimental Construction Bureau "Hydropress" (OKB HP). Podolsk The U.S.
delegation participated in meaningful discussions regarding the work at "Hydropress" activities on April 25, 1991 and had an opportunity to tour the experimental facility.
In were made by "Hydropress" scientists and addition, presentations from Leningrad in the following areas:
experts Studies of molten corium and water interaction.
1.
- 2. Fluid mixing and heat transfer in the presence of non-condensibles in VVER-type steam generators.
effects of Boron crystallization on flow
- 3. Studies of the distribution in the primary system following a LOCA.
- 4. Studies of fluid mixing in the reactor downcomer following ECCS actuation in VVERs.
The discussions were followed by a brief tour of the "Hydropress" experimental facilities. The hydrodynamic test rig for testing fuel assembly hydraulic characteristics was toured first. This facility holds seven full height fuel assemblies and is used to study vibration
- effects, hydraulic resistance and flow included.
distribution in PWRs. High and low pressure rigs were The second rig examined was a loss of coolant accident test rig.
This was an integral test facility simulating a VVER-440. The facility was scaled in volume 1/2000 relative to the VVER-440 plant and used an electrically heated seven rod bundle for core simulation.
The staff also toured a test rig for departure from nucleate boiling studies. The facility tests full scale fuel assemblies at pressures up to 200 megapaschals.
The "Hydropress" staff also pointed out the remains of a 1/5 scale mockup of a
four loop VVER which was used to study overall hydraulic loep characteristics in the VVER primary system.
I 4
1.V.Kurchatov Atomic Energy Institute (KAEI), Moscow i
prior to the meeting at "Hydropress",
the delegation met at Institute on April 25, 1991 to continue the discussions Kurchatov on natural circulation and thermal hy.draulic research studies.
The final meeting of this special U.S.
delegation to review USSR passive reactor designs and research took place at the Kurchatov Institute on April 26, 1991.
This session included the distinguished scientists and engineers from Leningrad and Dimitrovgrad as well as the accomplished representatives from Kurchatov Institute.
A detailed discussion of the VK-50 was provided by the Scientific and Research Institute of Atomic Reactors, Dimitrovgrad. The delegation also discussed emergency
~~
power
- supplies, the VVER 500 design and toured the B-1000 l
critical facility.
l l
RESULTS OF DISCUSSION i
l and l
The U.S. delegation heard many presentations regarding ongoing proposed reactor safety research in the Soviet Union. Because the U.S.
delegation was composed of members from two U.S.
government agencies (NRC and DOE) and from two U.S.
nuclear industry I
organizations (Westinghouse Electric Corporation and the Electric power Research Institute), interests in the research proposed by 1
l the USSR varied and were different for each organization represented in the U.S. delegation. Therefore, the interests of j
each organization are discussed separately below.
t I
i I.
U.S. Nuclear Regulatory Commission (U.S.NRC) l l
The U.S.
NRC representatives were impressed overall with the l
capabilities and proposed research of the various Soviet organizations visited. Based on areas of current importance to the
- NRC, NRC has identified an interest for potential further interactions with the USSR on the following areas:
l Predictions of
- 1. Hydrogen Behavior during Accident Conditions I
hydrogen behavior, hydrogen distribution in containments.
l l
2.
Thercal Mixing - thereal mixing in vessel downcocer during various transient and accident conditions.
3.
Corium-Water Interaction experimental and associated analytical work dealing with that portion of severe accidents when the molten core relocates to the lower hes.iaphere of the vessel.
5 l
4 The NRC believes the most appropriate way to effect further interactions is for the NRC to further study and evaluate the proposals - and to respond to the Soviet organizations through the
+
Kurchatov Institute.
The NRC representatives also noted that any further followup and initiation of formal cooperative agreements in these specific areas be in the form of a bilateral cooperative research agreement between the NRC and the Kurchatov Institute. This arrangement between the NRC and the Kurchatov Institute and the designation of the Kurchatov Institute as the USSR organization responsible for coordinating and monitoring future collective USSR institute efforts was agreed by the U.S.
and USSR delegations on April 26, 1991.
Therefore the NRC:
l
(
(a) will send to Kurchatov Institute a sample bilateral agreement currently in place between the NRC and other international organizations in order to familiarize Kurchatov Institute with this type of agreement.
I (b) based on the further study and evaluations, the NRC will l
(
further consider and subject to the NRC Commission and U.S. Government approval, as appropriate, l
the preparation of a draft bilateral agreement describing l
proposed cooperative research. This agreement would take the form of NRC participation in ongoing or proposed Soviet research program. Contributions could be financial or in-kind.
l II.
Westinghouse Dr. Lawrence L. Hochreiter, Consulting Engineer, Nuclear Safety Department, Westinghouse Electric Corporation was very favorably impressed with the size complexity and breadth of the research facilities at the different installations the delegation visited this week. The capabilities of the facilities cover the ranges of conditions that would be of interest for Westinghouse light water reactors. The r.anufacturing capability observed at Nizhny Novgorod was also impressive. Dr. Hochreiter plans to take the information given to him, along with his report, to those organizations within Westinghouse to see if there is interest in cooperative program between the institutes and that particular Westinghouse organization.
l l
6
1 III.
Electric Power Research Institute (EPRI) impressed with the high level of expertise displayed EPRI was very by the Soviet experts and also with the quality of test facilities which were visited. EPRI and the Soviets have worked cooperatively in some severe accident experiments in the USA. EPRI continues to be interested in severe accident research as well as passive features for advanced light water reactors. It is also possible that EPRI would be interested in development work on electric storage batteries if that work could be applied to lens expensive, high capacity batteries for use in electric automobile propulsion.
IV.
U.S. Department of Energy (U.S. DOE)
Dr. Peter M. Lang received a very favorable impression, shared by the other members of the U.S.
delegation, and will consider working with or through the U.S.
industry on possibilities of future cooperative efforts with the USSR.
V.
Other considerations The Soviet side will provide the U.S.
side with information related to the cost estimates. The Soviet side will also collect the proposals from various institutes and transmit them as a singe document to the U.S.
side.
In addition to the results achieved above, the USSR has committed to fully discuss batteries used in emergency D.C.
power applications in May, 1991 during the meeting in the U.S.
with Working Group 2. This discussion topic is addressed in Appendix V, topic number 5.
Appendices There are five appendices. Appendix IV, USSR proposals for future
- work, represents the collective input from the various USSR institutes visited by the U.S. delegation during the period April 22-26, 1991. These proposals, as assembled and coordinated by the Kurchatov Institute, will be considered further and if deemed appropriate will be persued by the individual delegation's organizations, including the United States Nuclear Regulatory Commission, Electric Power Research Institute, Westinghouse Electric Corporation and the United States Department of Energy.
7 I
l
In conjunction with the interest expressed by the U.S.
delegation representatives, as indicated above in the "Results of Discussion" section, the USSR proposals will be considered. This may require further discussions and correspondence initiated by the individual organizations to develop more fully specific tasks and proposals.
Specifically, the U.S.
NRC will conduct and direct any further U.S.
NRC discussions regarding USSR institute capabilities and considerations for future work through the Kurchatov Institute.
Appendix V represents questions and discussion topics the U.S.
propesed for this visit and which the USSR used to focus its presentation efforts.
The Appendices include the following information:
I.
Agenda II.
List of Participants III.
List of Documents and Oral Reports Presented by the USSR IV.
USSR Proposals for Future Work the USSR Proposed Questions and Discussion Topics during V.
Laboratory Visit, April 22-26, 1991 Signed in Moscow, USSR on April 26, 1991.
USSR Co-Leader:
U.S. Co-Leader:
O g 1
[$4dk W4 ds
/t!mes H. Sniezek d
Victor A.
Sidorenko 8
... -. _ =
. = _.
APPENDIX 1 AGENDA Monday, April 22 Heeting with the JCCC$RS Soviet leaders 9.30-14.30 at Kurchatov Institute Presentations 14.30-15.45 Lunch at Kurchatov Institute 16.00-16.40 Visit to " GAMMA" Reactor Facility 16.40-17.20 Visit to "KC" Thermophysical RIG Dinner hosted by the Soviet part of JCCCNRS 19.00 i
Tuesday, April 23 10.00-17.00 Visit to Physics & Power Institute in Obninsk l
Departure to Nizhny Novgorod (Charter Flight) 19.00 Wednesday, April 24 i
10.00 Visit to "MASHINOSTROENIE" Design Bureau l
19.00 Departure to Moscow (Charter Flight) l Thursday. April 25 9.00-11.00 Meeting at Kurchatov Institute Discussion of the results of visits to Obninsk and Nizhny Novgorod f
Presentations l
12.30-17.00 Visit to "Hydropress" Design Bureau (Podolsk) i Friday, April 26 Final Meeting at Kurchatov Institute 1
9.00-Signing of the demorandum i
14.30 Lunch ct Kurchatov Institute 9
APPENDfX 23 LIST OF PARTICIPANTS U.S.
Participants:
Co-Leader:
James H. Sniczek, Deputy Executive Director for Nuclear Reector Regulation, Regional Operations and Research, United States Nuclear Regulatory Commission Other
Participants:
United States Nuclear Regulatory Commission:
Director Division of Systems Research, Brian W.
- Sheron, Office of Nuclear Regulatory Research Timonthy E. Collins, Section Chief, Reactor Systems Branch, Divisions of Systems Technology, Office of Nuclear Reactor Regulation Jacob F. Wechselberger, Senior Regional Coordinator and Program Engineer, Office of the Executive Director for Operations Gordon Fowler, Jr., Project Manger for U.S.-USSR Cooperation, International Programs United States Department of Energy Peter Michael Lang, Project Manager, Office of LWR Safety and Technology Electric Power Research institute Advanced William H. Layman, Senior Technical Advisor, l
Reactors Development Westinghouse Lawrence L. Hochreiter, Consulting Engineer, Nuclear Safety Department f.
Interpreter Joseph Lewin l
i 10
USSR
Participants:
MINISTRY OF NUCLEAR POWER AND INDUSTR'Y, MOSCOW SIDORENKO V.A.,
First Deputy Minister GUTZALOV A.T.,
Assistant to the First Deputy Minister IVANOV V.A., Division Head SELEZNEV V.S.,
Expert l
KURCHATOV ATOMIC ENERGY INSTITUTE, MOSCOW PONOMAREV-STEPNOY N.N.,
First Deputy Director l
KUKHARKIN N.E.,
Department Head ASMOLOV V.G.,
Division Head SUKHORUCHKIN V.K.,
Laboratory Head i
SOKOLOV I.N.,
Laboratory Head KAPLAR E.P.,
Leading Researcher LEPPIK P.A.,
Laboratory Head PAKHOMOV V.P.,
Laboratory Head KOBZAR L.L.,
Laboratory Head SILIN V.A.,
Leading Researcher ELKIN I.V.,
Leading Researcher KONDRATIEV R.V.,
Leading Researcher ROMANOV E.V.,
Researcher ZAVALSKY V.A., Senior Researcher 11
l DOROFEEV S.B.,
Laboratory Head MALKIN S.D., Division Head KEVORKOV L.R.,
Laboratory Head PAVSHUK V.A.,
Division Head PAVELKO V.I.,
Laboratory Head G.M.KRZHIZHANOVSKY STATE RESEARCH POWER INSTITUTE (ENIN),
MOSCOW DUBROVSKY I.S., Senior Researcher CENTRAL BOILER AND TURBINE INSTITUTE, LENINGRAD TERENTIEV I.K.,
Deputy Director KOSTAREV V.V.,
Laboratory Head FEDOROVICH E.D., Division Hear' RESEARCH INSTITUTE OF NUCLEAR REACTORS, DIMITROVGRAD KUPRIENKO V.A.,
Deputy Director ESCHERKIN V.M.,
Chief Engineer SHMELEV V.E., Senior Researcher EXPERIMENTAL DESIGN BUREAU OF MACHINE BUILDING, NIZHNY NOVGOROD MITENKOV F.M.,
General Designer Director SAMOILOV O.B.,
Chief Designer, First Deputy Director KOMAROV Y.V.,
Chief Engineer PANOV Y.K.,
Chief Designer, Deputy Director l
12
KOSTIN V.1, Chief Designer. Deputy Director EUTYEEN L.N.,
Deputy Director RUCHIN V.S. Deputy Director BAEIN V.A.,
Chief of Department KUUL V.S., Chief of Department KALENTYEV V.I., Chief of Department DANILOVSKY V.S.,
Chief of Department LABEDEV V.D.,
Head of Designer Group RAZUMOV D.P, Head of Designer Group FALKOV A.A.,
Engineer PHYSICS AND POWER INSTITUTE, OBNINSK KIRILLOV P.L., Department Head SELIVANDY V.M., Division Head USHAKOV P.A.- Division Head o
ARKHANGELSXY V.V.,
Head of Department SHARYPIN V.I.,
Laboratory Head l
SUDNITSYN O.A.,
Laboratory Head VOROBJEV V.A., Laboratory Head EFANOV A.D.,
Laboratory Head OPANASENKO A.N., Senior Researcher POHETKO R.S., Senior Researcher i
l BELOGORTSEV Yu.I.,
System Engineer CHERNUKHIN V.L.,
System Engineer MASAGUTOV R.F., Senior Researcher KAPTUROVA R.I., Department Head Assistant 13
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"LUCH" RESEARCH AND PRODUCTION ASSOCIATION TCHEREPNIN J.S.,
Department Director "HYDROPRESS" DESIGN BUREAU, PODOLSK FEDOROV V.G., First Deputy Director, Chief Designer SKOTNIKOV A.P., Department Head DRAGUNOV Yu.G., Division Head LOGVINOV S.A.,
Division Head ROGOV H.F., Division Head BEZRUKOV Yu.A., Group Head GOLOVKOV L.I.,
Leading Designer MACHINE-BUILDING DESIGN BUREAU TEPLENTCHUK O.V., Division Heed REMIZOV H.A.,
Division Deputy Head SNETKOV V.G., Group Head l
L i
i 14 l
APPENDIX III LIST OF DOCUMENTS AND ORAL REPORTS PRESENTED BY USSR j
1.
By Kurchatov Institute:
Pavelko V.I.,
Rychev A.S.
1.1. Noise And Oscillator Experiments To Determine Dynamic Properties Of The " GAMMA" Nuclear Reactor Rig 1.2. Vakar H., Pakhomov V.
Electrochemical Devices For Hydrogen Concentration And pH Hessurements In The Coolant Of Water-Cooled Reactors Romanov E.V.,
Zavalskyi V.P.
1.3. Combined Model For Investigation Of NPP Non-Steady Processes 1.4.
Kaplar E.P.
The " GAMMA" Nuclear Thermoelectric Fari ity (NTEF)
Prototype Of Independent Unattended Energy Soarces of Small Power Level 1.5. Kondratiev F.V.
Natural Circulation Circuit Studies At The " GAMMA" Nuclear Thermoelectric Facility 1.6.
Leppik P.A.
On Investigat ions Of The Stability Of Hydraulic And Neutron Processes In The Vessel-Type Boiling Water Reactors With Natural Circulation 1.7.
Leppik P.A.
Stationary Mode Stability In Self-Controlled Nuclear Thermoelectric Systems With Natural circulation of " GAMMA" Type f
V.Escherkin, Yu.Chechetkin, V.Shmelev 1.Sokolov, 1.8. Investigation Of Boiling Vessel-Type Reactor (VK-50)
Performance I.N.Sokolov, N.N.Smirnov 1.9. Many-Dimensional Numerical Studies Of Convective Fluid-Disperse Gas Flow In Common Riser 1.10. I.V.Elkin Integral Test Facility For VVER Safety Research (ITF-VVEP)
S.D.Malkin 1.11.
Development of Math Mode)ing Methods For Parallel Channels i
Simulation During Severe Accidents And For Natural Circulation Conditions 15
.. - =
._~
i V.P.Zavalskyi l
1.12. On The Main Results Obtained From AST-500 Reactor Model (KS Thermophysical RIG) And Further Development G.N.Kruzhilin, 1.S.Dubrovsky 1.13. On Appropriateness of Steam Capture and Separation in BWRs L.R.Kevorkov 1.14. Proposal On Joint Works On Development Of The Cooling System With The Accelerator Of Circulation For BWR 1.15. S.B.Dorofeev St.maary of hydrogen combustion detonation. DDT experiments a: d modelling 1.16. V.A.Silin in the reactor Organizatien of studies of corium confinement vessel 2.
By OKBM specialists:
2.1. F.M.Hitenkov Report on OKBM activities 2.2. V.S.Kuul Integral reactor model for thermohydraulic study at normal and emergency regimes 2.3. G.I.Tarasov in Investigations of thermal physics ef fects and processe's I
integral nuclear reactors with built-in steam gas pressurizers 2.4. V.A.Babin Thermohydraulic study of the vertical shell-and-tube heat l
exchanger model 2.5. V.I.Kostin Nuclear power plants main circulators 2.6. V.D.Lebedev NPP main circulators hydrodynamic seals 2.7. D.P.Razumov Nuclear power plants valves l
2.8.
L.N.Kutyeen OKBM experimental base 2.9. Documents on the design and the safety analysis of NPP AST-500 (6 volumes) 16
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3.
By Physics and Power Technology Institute (Obninsk):
Natural circulation under conditions of single-phase and 3.1. two-phase fic. s.
3.2. Heat and mass transfer, critical heat fluxes and hydrodynamics under steady-state program verification.
3.3. Stratification and mixing of different temperature coolant flows in NPPs.
3.4. Hydrodynamic stability of flow.
3.5. Methods and algorithms for diagnostic of NPP operating conditions using acoustic and thermal noises.
3.6. Fuel melting and its movement; molten corium interaction with water and reactor vessel.
3.7. Processes in reactor containment during LOCA.
3.8. Hydraulic testing of separate NPP components.
heat and mass 3.9. Theoretical and experimental investigations o, transfer on containment models, including 1, 8,
100, 250 and 3000 cubic meter models.
4.
By Polzunov Central Boiler and Turbine Institute, Leningrad:
4.1.
E.D. Fedorovitch Possibilities of large scale steam / water test facilities of Central Boiler and Turbine Institute Kostarev 4.2.
V.V.
Application of CKTI dampers for protecting NPP equipment and structures agains dynamic and seismic response.
5.
By "Hydropress":
5.1.
Rogov H. F.
Information On VVER-500 Project l
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Bezrukov Yu.A.
5.2.
Fuel-Water Interaction (Experimental Results obtained in Helt Semipalatinsk)
Logvinov S.A.
i 5.3. Studies on Steam Condensation In Steam-Generator In the Presence of Non-Condensable Gases 5.4. Teplentchuk O.V.
Information on Main Circulationg Pump 5.5. Golovkov L.I.
Information On NPP Equipment By "Luch" Research and Production Association:
6.
6.1.
Cherepnin Ju.S.,
Experimental basis of the "Luch" Research and Production Association.
7.
By Research Institute of Nuclear Reactors:
7.1.
Kuprienko V.A.
Experimental capabilities of the Research Institute of Nuclear Reactors.
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-.,.e e.--
APPENDIX IV USSR PROPOSALS FOR FUTURE WORK The following are topics suggested by institutes of the USSR on possibl joint efforts.
These will be further considtred, as appropriate, and more formally proposed during the exchange of future correspondence.
A.
RESEARCH TOPICS:
- 1. Heat exchange studies of coolant natural circulation circuits:
1.1. Studies of thermophysical processes under normal, transient and accident conditions at mockups and large-scale models of nuclear reactors with the natural circulation, including the presence of non-condensable gases.
1.2.
Studies of transient and accident modes of light water reactors of integral type together-with the neutron kinetics imitator.
1.3.
Verification of programs to calculat-processes of thermo-mass transfer and stability parameters and auto-oscillations in natural circulation systems.
- 2. Safety improvement of light water power reactors and development of new generation reactors with ultimate safety:
2.1. Studies at integral models of light water power reactors of new generation in accordance with the agreed
- program, including the development of passive safety systems.
2.2. Seismic stability criteria and analysis for NpP equipment and pipings. Protecting NpP equipment against seismic and dynamic impacts based on new HVD CKTI dampers technology (snubber program).
19
l 2.3.
A complex of activities on computer and experimental simulation of severe accidents.
(core degradation; interactions between the corium and the vessel, between the corium and concrete, between the corium and water; fuel and fission product release and migration in the Containment; j
hydrogen safety, etc.).
2.4.
Material testing studies of fuel elements and materials sampics with simulation of transient and accident modes.
2.5.
A complex of investigations of accidents with a fast power increase, using the irradiated fuel of ' 40 MW day /t.
2.6.
Studies of flow mixing with different dencity and temperature (in case of circulation loop rupture) and with boric acid injection.
2.7.
Testing of thermomechanical equipment, isolating and regulating valves, safety and check valves.
2.8. Reliability studies of main circulation pump seals under loss of cooling water conditions.
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- 3. Development of independent nuclear power systems of small power level 3.1 Development, including on the basis of studies at the " GAMMA"
- rig, of international regulations and norms for design, construction and operation of independent nuclear power systems of a small power level.
3.2. Development of basic principles and experimental studies of the remote dispatcher system fragments and cockups to ensure early identification of operating deviations and to provide the information well in advance the reactor trip.
3.3, Market studies and development of cooperation to manufacture l
and construct independent unattended nuclear power systems of a small power level, t
a 20
B.
EXPERIMENTAL BASIS.
Experimental facilities Research topics Reference to-the (see Section A) list of reports
- 1. KC Rig 1.1.
1.2.
1.3.
1.3.
1.12.
- 2. VK-50 1.1.
1.2.
1.3.
1.6.
1.8.
1.13 2.3.
2.6.
2.7.
3.1.
3.2.
1.1.
1.4.
1.5.
- 3. Gamma 1.7.
4.
KOPER 2.3.
1.15.
- 5. UTR 2.3.
1.15.
6.
Reactors and rigs in 2.4.
7.1.
Research Institute of Nuclear Reactors
- 7. Rigs of Physics and 1.1.
1.2.
1.3.
3.1.
- 3.9.
Power Institute 2.3.
2.6.
3.2.
- 8. Rigs of Central Turbine 1.1, 2.2.
2.3.
4.1.
4.2.
and Boiler Institute
- 9. Reactors and rigs of 2.3.
2.4.
6.1.
"Luch" Research and Production Association
- 10. Rigs of OKBH 1.1.
2.1.
2.7.
2.2.
- 2.8.
2.8.
II. Rigs of "Hydropress" 1.1.
1.3.
2.6.
5.2.
5.3.
5.5
- 12. Rig of ITF-VVER 1.1.
1.2, 1.3.
1.10.
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.. =..- _.
s' APPENDIX V PROPOSED QUESTIONS AND DISCUSSION TOPICS DURING THE USSR LABORATORY VISIT, APRIL 22-26, 1991 l
The U.S. side proposed in a preliminary way the following topics and issues for discussion:
1 1.
Discussion of natural circulation testing and capabilities at these facilities and any others of particular interest in this area:
"KC" Thermophysical RIG
- " Gamma" Reactor Facility a.
Discussion of the parameters of the test facilities, including dimensions and configurations of t h(
test apparatus. This would encompass the operating par ame; ers of the facilities to include pressure, temperature, scaling factors, flow rates and power capability or limitations,
- b. How is heat loss controlled?
facility instrumented to measure temperature,
- c. How was theflow and other operating parameters of interest?
- pressure,
- 2. Heat transfer and possible flow stratification in the presence of non-condensibles during natural circulation flow for primary and containment systems.
For
- example, consider natural circulation through the steam generator and other decay heat removal systems, under normal shutdown and accident conditions, including severe accidents. There is also an interest in mixing and flow stratification in containment for hydrogen concerns.
any facilities with the capability of performing Are there hydrogen research in a high temperature steam environment?
a.
Are there currently any research experiments in this ares.
There is a need to explore hydrogen detonability in a high steam temperature environment.
22 2
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- b. For a rodded core geometry, are there any capabilities to examine uranium-dioxide melt progression inside the reactor vessel. Does the hemispheric dome and determine the resulting failure mechanism (s).
3.
Mixing of two fluid streams of different temperature and density in reactor geometry; for example, boron injection and coolant injection under stagnant conditions.
- a. Specifically, th4s should be considered for a gravity drain system flow into the reactor.
- 4. Valve reliability data during upset conditions, including check valves, motor operated valves and depressurization system valves.
This would include design performance information under limiting design conditions. There is particular interest in check valve experience in high/ low pressure interface applications, and the effect of extended time periods between actuations on differential i
pressure required for valve opening.
I
- d. What type of test facilities and programs are there for testing valves?
- b. What are the programs used to test isolation valves under limiting operating conditions?
- c. Are there any programs to perform reliability and limiting condition tests fer large depressurization system valves?
l What data was gathered during these tests?
- d. What has been the experience in conducting these test programs at the identified facilities?
- e. What is the uncertainty associated with the facility instrumentation and how is the uncertainty evaluated?
- f. What are the limiting test conditions (i.e.,
flow rates, pressure, temperature) achievable in operating test rigs.
5.
Life cycle and capacity information for batteries used in emergency D.C.
power applications.
Discussion sho'ald provide inforcation on maintenance and test programs, including loading rate limitations.
23
e pump seal tests under loss of seal cooling conditions. There is 4
6.
interest in the VVER-1000 reactor coolant pump seal particular and Discussion should include tests performed and results, design; test conditions and parameters,
- a. Have there been any two phase flow experiments conducted on canned rotor pumps? Does equipment exist +o conduct this type of experiment?
is the test apparatus instrumented during th* loss of
- b. How seal cooling experiment?
- c. Where and what measurements are taken and what conditions are used for the test?
- 7. General questions applicable to the areas above.
- a. Describe the quality assurance procedures and precautions used while conducting experiments. What pre-test is the verifications and measurements are performed? How experiment documented?
- b. Describe the test operating history and exper'ence of these facilities, including the range of test conditions-for the experiments and the extent of use,
- c. What are the considerations in scaling a test facility' 24
.