ML20205N455

From kanterella
Jump to navigation Jump to search
Partial Response to FOIA Request for Documents Re Accident at Chernobyl Nuclear Power Station.Forwards App G Through Documents.Documents Also Available in PDR.NUREG-1250, Rept on Accident at Chernobyl..., Available from Gpo
ML20205N455
Person / Time
Issue date: 03/30/1987
From: Grimsley D
NRC OFFICE OF ADMINISTRATION (ADM)
To: Taylor J
DALLAS TIMES HERALD, DALLAS, TX
Shared Package
ML20205N459 List:
References
FOIA-86-335, RTR-NUREG-1250 NUDOCS 8704030031
Download: ML20205N455 (20)
v • d • e


Text

~

r--

U.S. NUCLEAR RE1ULATORY COMMISS N N..c poia neoutsi Nuustass

^

86-335 f "%

3*

i .a] M -,.o~,,1m I**^' I MI '*'

.i RESPONSE T3 FREEDOM CF INFORMATION ACT (FOIA) REQUEST s

\ ^

- 30 W (e so.e DeCKET NUMetAiss ur especebes lREQutSTER Mr. Jack H. Taylor, Jr.

PART 1.-MECORDS RELEASED OR NOT LOCATED (See checked bones)

No agency records subject to the request have been located.

No additional agency reentds subpect to the request have been located.

Agency records subject to the request that a o identred in Appendix are already available for publec inspection and copying in the NRC Ptblic Document Room, 1717 H Street, N.W., Washington, DC.

Agency records subject to the request that are identrfied in Appendix G t h rm 9 are being made availabie for public inspection and copying in the NRC Public Document X aoom.1717 H Street, N.W., Washington, DC, in 6 folder under the FOIA number and requester name.

  • The nonproprietary version of the proposaHal that you agreed to accept in a telephone conversation with a member of my staff is now being made avalable for public inspection and coying at the NRC Public Document Room,1717 H Street, N W., Washington, DC. in a folder under this FOIA number and requester name.

Enclosed is information on how you may obtain access to and the charges for copying records placed in the NRC Public Document Room,1717 H Street, N.W., Washington, DC.

X Ae'acy r*ca'd' 'ub>'c' 'a 'h* au' '"c'o****^"Y *pp'ic*b ch*'** 'o' c *** a' th' c*'d* p' vid*d *"d p*vm*"' p' c'd"*' "od '" th* *****" **c'i a-

"'c'd"bi*c*'h'""**'"'**b""'"'d'*'"'h*''''S*"c''"'*'"ddic""**"-

X In view of NRC's response to the request, no further action is being taken on appeal letter dated PART ll.A-INFORMATION WITHHELD FROM PUBLIC DISCLOSURE Certain information in the requested records is being withhold from public disclosure pi rsuant 'o the FOIA exemptions described in and for the reasono stated in Part II, sec-tions B. C and D. Any released portions of the documents for which only part of the record is being withheld are being made available for public inspection and copying in the NRC Public Document Room,1717 H Street, N.W., Washington. DC, in a folder under this FOlA number and requester name.

Comments

  • Except that records containing copyright information are being made available for inspection only in the NRC PDR as follows: G2 # 3 through G # 7 G6, G7, G8, G10 through G16, G19, G20, and RSW6.

For your information, a computer print-out list of other PDR records relating to the Ch:rnobyl incident is enclosed. These records are not subject to your request but they may ~

be of interest to you.

Also, On February 6,1987, the Commission approved the release to the NRC's Public Document Room of NUREG-1250, " Report on the Accident at the Chernobyl Nuclear Power Station" (209 pgs 3

Copies of NUREG-1250 are available for $10.00 from the Superintendent of Documents U.S. Government Printing Office P.O. Box 37082 Washington DC 20013-7082 and National Technical Information Service L U.S. Department of Commerce

Springfield VA 22161 l

l

'WA"' 7"$lr" "' "%

l 1 '

mRc FORM as4 m.n 8704030031 870330 1

, ,, .s, PDR FOIA

[ TAYLORS6-335 PDR _ ,

'o h i F01A-86-335 APPENDIX G RECORDS MAINTAINED IN THE PDR UNDER THE AB0VE RE0 VEST NUMBER

1. 5/4/86 Report: " Design Features of the Soviet RBMK-1000/Chernobyl - 4 Reactor," by Walter Mitchell, III, P.E. (44pages)
2. 5/6/86 Memo for Fraley from Denton,

Subject:

Chernobyl Reactor Event w/ enclosures - Incex and publishea articles (62 pages)

3. 4/ English Translation from Atomnaya Energiya, Vol. ,

No. pp. , " Fuel Elements of the RBMK - 1000 Reactor", by V.G..Aden, et. al. (6 pages)

4. English Translation from Atomneya Energiya, Vol. No.

pp. , "Pcwer. Distribution Monitoring and Control for a RBMK Reactor", by I Ya Emelyanov, et. al. (6 pages)

5. English Translation from Atomnaya Energiya, Vol. No.

pp. , "The Leningrad Nuclear Power Station and the Outlook for Channel Type BWR's", by A.S. Petrosyaitts, et. al. (11 pages)

  • 6. 6/81 English Translation (pp. 338 - 342) from Atomnaya Energiya-Vol. 50, No. 6, pp. 381 - 384, " Steam Effects and Reactivity Coefficients of the Beloyarsk Nuclear Power Station Reactors" by V.P. Andrews, et.al. (4 pages)
  • 7. 8/84 English translation (pp 512 - 517) from Atomnaya Energiya Vol. 57, No. 2, pp. 67 - 91, " Safety Under Servicing Cooling Conditions for RBMK Reactors" by V.N. Smolin, et. al.

(6 pages)

  • .8. 8/84 English translation (pp 507 - 512) from Atomnaya Energiya Vol. 57, No. 2, pp. 83 - 87, "An Experimental Study of Emergency Cooling Conditions in RBMK Reactors on Load Disconnection" by V.N. Smolin, et. al. (6 pages)
9. 1981 English Article (pp. 16, 17, 98, 99, 18, 21, 92, 93, , 96, 95, 97, , 266, 267, Appendix 6-5, , 273) from MIR Publishers-Moscow, edited by V. Dubrovsky. (19 pages)
10. 6/84 English translation (pp 368-374) from Atomnaya Energiya Vol. 56, No. 6, pp 359-365, " State of the Art and Development Prospects for Nuclear Power Stations Containing RBMK Reactors" by E.V.Kulikov. (7 pages)
  • This publication contains COPYRIGHTED MATERIALS. A copy is available for public inspection in the NRC's Public Document Room (PDR).
6 Re: F01A-86-335 (Continued)
  • 11. 4/79 English translation (pp 259 - 262) from Atomnaya Energiya Vol. 46, No. 4, pp. 219 - 222,'" Change in the Fuel Component of Cost of Electrical Energy During a Transitional Operating Period of a High-Powered Water-Cooled Channel '

Reactor (RBMK)" by S.V. Bryunin, et. al., (4 pages)

  • 12, 5/84 English Translation (pp. 294-297) from Atomnaya Energiya Vol. 56, No. 5, pp. 280-282, "Underloading Additional Absorbers from the RBMK-1000 Core" by N.V. Isaev, et cl. (4 pages);
  • 13. 12/82 English translation (pp. 816-824) from Atomnaya Energiya Vol. 53, No. 6, pp. 367-373, " Physical Characteristics of an RBMK Reactor in the Transitional Period," by V.S. Romanenko

& A.V. Krayushkin (9 pages)

  • 14. 2/80 English translation (pp. 116-119) from Atomneya Energiya Vol. 48, ho. 2, pp. 102-103, "Seconcary Swelling of Graphite" by Yu S. Virgil'ev, et. al. (4 pages)
  • 15. 4/79 English Translation (pp. 262-266) from Atomnaya Energiya Vol. 46, No. 4, pp. 222-227, "Optimizatior, of the Safety Margin to the Critical Load of the Heat-Releasing Assemblies in a High-Power Water-Cooled Channel Reactor" by S.V. Bryunin, et. al. (5 pages)
  • 16. 7-8/77 English translation (pp. 438-450) from Nuclear Safety Vol. 18, No. 4, pp. 438-450, "The Russian Approach to Nuclear Reactor Safety" by J. Levin. (13 pages)
17. 4/1/82 English translation (pp. 18-19) from Alma Ata Kazakhstanskaya Pravda, p. 4, " Order-a Barrier to Fire:

Problems of Fire Prevention at Power Industry Facilities" by R. Nurseitov. (2 pages)

18. 1984 English translation (pp. 65-73) from Sorraniye Postanovleniy Pravitel'stva SSSR No. 20, pp. 355-364,

" Examination of Safety Regulations in Nuclear Power Plants" by N.A. Tikhanov& M.S. Smirtyukov. (9 pages)

  • 19. 3/84 English translation (pp. 154-159) from Economicheskoye Sotrudmichestvo Stran Chienov SEV, pp. 47-49, " Insuring the Radiation Safety of AESs" by A.B. Alfonso & W. Stregofer.

(6 pages)

  • 20. 4/79 English translation (pp. 267-272) from Atomnaya Energiya Vol. 46, No. 4, pp. 227-232, " Deformation of an Energy Release Field in a High-Powered Water-Cooled Channel Reactor (RBMK)"

by A.N. Aleksakov. (6 pages)

  • This publication contains COPYRIGHTED MATERIALS. A copy is available for public inspection in the NRC's Public Document Room (PDR).

4-Re: F01A-86-335 APPENDIX H ASSOCIATED PRESS TELETYPE MESSAGE RECORDS MAINTAINED IN THE PDR UNDER THE ABOVE REQUEST NUMBER

1. 5/3/86 10:44 EDT (1 page)-
2. 5/3/86 10:50 'EDT (1 page)
3. 5/3/86 10:56 EDT (1 page)
4. 5/3/86 13:58 EDT (1 page)
5. 5/5/86 12:47 EDT (1 page)
6. 5/9/86 9:01 EDT (1 page)
7. 5/9/86 9:07 EDT (1 page)
8. 5/9/86 9:12 EDT (1 page)
9. 5/9/86 9:18 EDT (1 page)
10. 5/9/86 9:56 EDT (1 page)
11. 5/9/86 10:31 EDT (1 page)
12. 5/9/86 10:35EDT(1page)
13. 5/9/86 11:16 EDT (1 page) t i

l

, -- - - , , .-,,,,,-,-.n. -,,-------,-,.-r- ,-------,_ng.,-,,,v-,- . - - . - -- - - - - - - , . - - - , - - - . - - , + , - - - , , , , , - , - -

D

'N' Re: F01A-86-335 APPENDIX I RECORDS MAINTAINED IN THE PDR UNDER THE AB0VE REQUEST NUMBER

1. 5/6/86 Telegram to multiple addresses from NRC - IP

Subject:

.Information on Effects of. Soviet Accident (3 pages).

2. 5/8/86- Memorandum for Smith from Speis,

Subject:

Attached Offer of U.S. Aid (3 pages).

  • 3. 5/8/86 Status Briefing on the Chernobyl Nuclear Accident Presented to the Advisory Ccmittee on Reactor Safeguards (49 pages).
4. .5/9/86 List of published NUREGS, Articles, Testimony, Statement,.

and list - Sumary of Environmental Results from hRC Licensees, May 9, 1986(2pages).

5. 5/12/86 Sumary of Environmental Results from NRC Licensees (2 pages).
6. 5/12/86 Memorandum for Distribution from'Speis,

Subject:

Daily Status' Report - May 12,1986(2pages).

7. 5/13/86 Status briefing on the Chernobyl Nuclear Accident -

Presentation to the Comission (21 pages).

8. 5/13/86 'Sumary of Environmental Results from NRC Licensees w/ cover page (3'pages).

c- 3 RE: F01A-86-335 APPENDIX J INFORMATI0h ON THE S0VIET CHERNOBYL-ACCIDENT PROVIDED TO THE NRC BY THE IAEA

1. 5/7/86 Cover sheet; Handwritten notes; Sunnary of Radiological situation in Poland; Isotopic Composition in Air Concentration in Warsaw between April 28 - May 3, 1986; Measurensent from North-Western Yugoslavia on May 5, 1986; (9 pages)
2. 5/7/86 Cover Sheet; Radiological Situation in Poland (4 pages)
3. 5/9/86 Cover Sheet; Handwritten notes on raciation measurements in Austria (13 pages)
4. 5/14/86 Transmission No. 6 from USSR re: Radiation levels on 5/14/86 at seven locations (2 pages).

Re: F01A-86-335 APPENDIX K ATOMIC INDUSTRIAL FORUM INF0 WIRE RECORDS MAINTAINED IN THE PDR UNDER THE ABOVE REQUEST NUMBER NUMBER DATE DESCRIPTION

1. 5/5/86 10:20 Subjects 1. NRC Request to U.S. Plants
2. State Department on Travel
3. Chernobyl Unit Three
4. EPA in Poland (1 page)
2. 5/5/86 12:10

Subject:

Connecticut Yankee Checks Students (1 page)

3. 5/6/86 10:58

Subject:

Emergency Planning Study (1 page)

4. 5/6/86

Subject:

Coalition calls for Reactor Shutdowns (2pages)

5. 5/6/86 15:39

Subject:

Russian Sequence of Events (1 page)

6. 5/8/86 10:25

Subject:

Chernobyl Isotopes (1 page)

7. 5/12/86 13:32

Subject:

Assessment of the Medical Situation In Chernobyl USSR (4 pages) i

Re: F01A-86-335-APPENDIX L NEA/0 ECD RECORDS MAINTAINED IN THE PDR UNDER THE AB0VE REQUEST NUMBER NUMBER DATE DESCRIPTION

1. 5/3/86 .NEA, TWX to Cunningham from Stadie re: special meeting on 5/9/86, with_har.owritten annotation _(1 page)

_ 2. 5/9/86 TWX -

Subject:

'Tchernobyl. Press Release on May 9 meeting of NEA CSNI (2 pages) 4

Re: F0IA-86-335 APPENDIX M RECORDS MAINTAINED IN THE PDR UNDER THE AB0VE REQUEST NUMBER NUMBER DATE- DESCRIPTION

1. 5/5/86 18:50:30 PRAVDA hews Story:129 (3 pages)
2. 5/5/86 18:34:51 PRAVDA News Story:131 (2 pages)
3. 5/5/86 18:39:18 PRAVDA News Story:13E (1 page)

Re: FOIA-86-335 APPENDIX N RECORDS MAINTAlhED IN THE PDR UhDER THE AB0VE REQUEST NUMBER

' NUMBER _ DATE DESCRIPTION

1. 4/29/E6 Public Announcement by GA Technologies, Inc... .

w/ attachment: three pages of English translation of a Russian publication reference: Publishing House of Foreign Ministry, Publication Number 291MS, Abstract Reactor RBM-K in English tengue, LT 4 Union Polygraph Production, Order 852/1. (6pages)

Re: F01A-86-335

' APPENDIX 0 PRECIPITATION DATA RECORDS MAINTAINED IN THE~PDR UNDER THE'AB0VE REQUEST-NUMEER NUMBER-- DATE DESCRIPTION

1. 4/25-5/3/86' Compilation of Precipitation Data from Selected Countries (13 pages)

I w

R Re: F0!A-86-335-APPENDIX P RECORDS MAINTAINED IN THE PDR UNDER THE AB0VE REQUEST NUMBER hUMBER DATE DESCRIPTION

1. 5/2/86 2:45 pm Report; Estimates of the Chernobyl Accident Severity Based on Radioactivity Measurements Provided by Sweden, Finland,'and other sources (12 pages)
3. 5/8/86 Note to Chaney from Senseney, subject: Response to Questions from May 6 hearing (1 page) 4

Re: F01A-86-335 APPENDIX Q IhP0 RECORDS MAINTAINED IN THE POR UhDER THE AB0VE REQUEST hUMBER DATE .0ESCRIPTION

1. 4/29/86~ Memo to Stello from Strahm, subject: Russian Nuclear Power Accident, w/ attachment (38 pages) 1 l

l

Re: F01A-86-335 APPENDIX R TWX RECORDS MAINTAINED IN THE PDR UNDER THE AB0VE REQUEST NUMBER NUMBER DATE DESCRIPTION ORIGIN: BELGIUM RB 1. 5/7/86 10:00(8pages)

ORIGIN: CANADA RC 1. 5/4/86 (3 pages)

2. 5/6/86 (12 pages)
3. 5/6/86 10:30(42pages)
4. 5/6/86 15:45(10pages) 5.- 5/9/86 11:10(9pages)

ORIGIN: DENMARK RD 1. 5/6/86 (12pages)

2. 5/13/86 (3pages)
3. 5/14/86 (23pages)
4. 5/14/86 (11pages)

ORIGIN: UNITED KINGDOM (ENGLAND)

RE 1. 3/86 (1page)NRPB-R182(Coverpageonly)

2. 3/86 (1page)NRPB-DL10(Coverpageonly)
3. 5/5/86 11:10(1page)

I t, . 5/8/86 (16pages)

ORIGIN: FINLAND l

RF 1. 5/1/86 (1page)

2. 5/2/86 (7pages)
3. 5/4/86 10:29(1page)

r Re: FOIA-86-335 (Continued)

4. 5/6/86 08:37 (1 page)
5. 5/7/86 07:24(2pages)
6. 5/7/86 (42pages)
7. 4/29/86 (1page)

ORIGIN: GERMANY RG 1. 5/4/86 07:01(3pages)

2. 5/5/86 14:20(11pages)
3. 5/7/86 (10pages)
4. 5/9/86 (6pages)
5. 5/10/86 17:09 (4 pages)

ORIGIN: ISRAEL RI 1. 5/8/86 06:27 w/ enclosures (4 pages)

2. 5/8/86 10:07(1page)
3. 5/12/86 07:49(2pages)

ORIGIN: JAPAN RJ 1. 5/4/86 03:46(1page)

2. 5/5/86 10:54(11pages)
3. 5/9/86 01:00 (Moscow) #1 Transmission (2 pages)
4. 5/9/86 04:32EST(1page)
5. 5/10/86 13:37#2 Transmission (2pages)
6. 5/11/86 12:52#3 Transmission (2pages)
7. 5/12/86 11:08#4 Transmission (2pages)
8. 5/14/86 03:25#5 Transmission (2pages)

ORIGIN: REPUBLIC OF KOREA RK 1. 5/7/86 00:45(1page)

2. 5/9/86 00:29(1page)
3. 5/9/86 20:15(1page)

r 7

Re:.FOIA-86-335 (Continued)

ORIGIN: MEXICO RM 1. 5/6/86 17:23(1page)

ORIGIN: NORWAY RN 1. 5/9/86 (3pages)

ORIGIN: PHILIPPINES RP 1. 5/9/86 (1page)

ORIGIN: SPAIN RSP 1. 5/12/86 (43pages)

ORIGIN: SWEDEN RSW 1. 4/29/86 05:21 (1 page)

2. 4/30/86 (10pages)
3. 5/1/86 (2 pages)
4. 5/2/86 19:00(SWE)(6pages)
5. 5/3/86 (8pages)
    • (17pages)
6. 5/3/86
7. 5/5/86 (2pages)
8. 5/6/86 (4pages)
9. 5/7/86 (5 pages) 10, 5/9/86 (7pages)
11. 5/13/86 (13pages)
    • This record contains COPYRIGHTED MATERIALS. A copy is available for publicinspectionintheNRC'sPubiteDocumentRoom(PDR).

Re: F01A-86-335 i (Continued)

ORIGIN: SWITZERLAND R5WI 1. 5/5/86 (4pages)

2. 5/7/86 (3 pages)
3. 5/9/86 (2pages)
4. 5/13/86 (6pages)
5. 5/14/86 (8pages)

G l

Re: F01A-86-335 APPENDIX S RECORDS MAINTAlhED IN THE PDR UNDER THE AB0VE REQUEST NUMBER

1. Undated (approximate 5/2/86) Memo for EPA from Spets. (5 pages)
2. 5/2/86 Memo.(3pages)
3. 5/5/86 Memo. (2 pages)
4. 5/5/86 12:36 pm to lhP0. (2 pages)
5. 5/5/86 1:00 pm to INP0. (2 pages)
6. 5/5/86 to DOE (2 pages)
7. 5/5/86 2:50pmtoGinneyHansen,AIF.(2pages)
8. 5/5/86 4:30 pm to Terry Blackmon, CECO. (3 pages)
9. 5/6/86 3:10 pm to Lars Hogberg, SKI. (1 page)
10. 5/6/86 to Theo Evers, Embassy of Netherlands. (9 pages)
11. 5/6/86 tot.Speis.NRCc/oLee.(5pages)
12. 5/6/86 to Fritz Wolff, DOE /EOC. (2 pages)
13. 5/6/86 Memo for Distribution from Speis. (2 pages) 14, 5/7/86 to Harry Celley, EPA (Crystal City). (2 pages) 15, 5/7/86 to S. Magnusson Iceland w/ enclosures. (15 pages)
16. 5/7/86 to D. Matthews, IE. (2 pages)

I

e FOIA-86-335 APPENDIX G RECORDS MAINTAINED IN THE PDR UNDER THE AB0VE REQUEST NUMBER

1. 5/4/86 keport: " Design Features of the Soviet R6MK-1000/Chernobyl - A Reactor," by Walter Mitchell, III, P.E. (44pages)
          • 2. 5/6/86 Memo for Fraley from Denton,

Subject:

Chernobyl Reactor Eventw/ enclosures-Indexandpublishedarticles(62pages)

3. 4/ English Translation from Atomnaya Energiya, Vol. ,

ho. pp. . " Fuel Elements of the RBMK - 1000 Reoctor", by V.G. Aden, et. al. (6 pages)

4. English Translation from Atomnoya Energiya, Vol. hc.

ap. , "Fcwer Distribution Monitoring and Control for a FBMK Reactor", by 1 Ya Emelyanov, et. al. (6 pages)

5. English Translation from Atomnaya Energiya, Vol. No.

pp. . "The Leningrad Nuclear Power Station and the Outlook for Channel Type BWR's", by A.S. Petrosyants, et. al. (11pages)

  • 6. 6/81 Enolish Translotion (pp. 336 - 342) frcm Atomnaya Energiya Vol. 50, No. 6, pp. 381 - 384, " Steam Effects and Reactivity Coe.fficients of the Beloyarsk Nuclear Pcwer Station Reactors" by V.P. Andrews, et.al. (4 pages)
  • 7. 8/64 English translation (pp 512 - 517) from Atomnayo Energiya Vol. 57, ho. 2, pp. 67 - 91, " Safety Under Servicing Cooling Conditions for RBMK Redctors" by V.h. Smolin, et. al.

(6 pages)

  • 8. English translation (pp 507 - 512) from Atomnaya Energiya 6/84 Vol. 57, No. 2, pp. ES - 67, "An Experimental Study of Emergency Cooling Conditions in RBMK Reactors on Load Disconnection" by V.N. Sinolin, et. al. (6pages)
9. 1981 English Article (pp. 16, 17, 98, 99, 18, 21n 92, 93, , 96, 95, 97. , 266, 267, Appendix 6-5, , 273) from MIR Publishers-Itoscow, edited by V. Dubrovsky. (19 pages)
10. 6/84 English translation (pp 368-374) from Atomnaya Energiya Vol. 56, No. 6, pp 359-365, " State of the Art and Development Prospccts for huclear Power Stations Ccutaining RBML Ruoctors' by E.V.hullkov, (7 pages)
  • This publication contains COPYRIGHTED MATERIALS. A co)y is available for public inspection in the NRC's Public Document Room (PD1).

?

i

\

Pe: FOIA-06-335 (Continued)

  • 11. 4/79 English translation (pp 259 - 262) from Atocinaya Energiya Vol. 46, No. 4, pp. 219 - 222 ." Change in the Fuel Component of. Cost of Electrical Energy During a Tronsitional Operating Period of a High-Powered Water-Cooled Channel Reactor (RBMK)" by S.V. Bryunin, et. al., (4 pages)
  • 12, 5/84 EnglishTranslation(pp. 294-297) from Atomnaya Energiya Vol. 56, ho. 5, pp. E60-282, "Underloading Antitional Absorbers from the RBMK-1000 Core" by N.V. Isaev, et. al. (4 pages)
  • 13, 12/82 English translation (pp. B16-824) from Atomnaya Energiya Vol. 53, i:o. 6, pp. 367-373, " Physical Characteristics of an RBMK Reactor tii the Transitional Period," by V.S. Romanenko

& A.V. Krayushkin (9 pages)

  • 14. 2/80 English translation (pp. 116-119) from Atoroneya Energiya Vol. 48, ho. 2, pp. 102-103, " Secondary Swelling of Graphite" byYuS.Virg11'ev,et.al.(4pages)
  • 15. 4/79 English Translation (pp. 262-266) from Atoanaya Energiya Vol. 46 No. 4, pp. 222-227, " Optimization of the Safety Margin to the Critical Load of the Heat-Releasing Assemblies in a High-Power Water-Cooled Channel Reactor" by S.V. Bryunin, et. al. (5pages)
  • lb. 7-8/77 Englishtranslation(pp. 438-450)- from Nuclear Safety Vol.16 No. 4, pp. 438-450, "The Russian Approach to Nuclear Reactor Safety" by J. Levin. (13pages)
17. 4/1/62 English translation (pp. 18-19) from Alma Ata Kazakhstanskaya Pravda, p. 4, " Order-a Barrier to Fire:

Problems of Firs Prevention at Power Industry Fac111th.s" byR.hursettov.(2pages)

18. 1904 Er.glish translation (pp. 65-73) from Sorraniye '

Postanovieniy Pravitel'stva SSSR ha. E0, pp. 355-364,

" Examination of Safety Regulations in Nuclear Power Plants"

, byN.A.Tikhanov&M.S.Smirtyukov.(9pages)

  • 19, 3/84 Englishtranslation(pp. 154-159) from Economicheskoye Sotrudmichestvo Stran Chlenov SEY, pp. 47-49, " Insuring the Radiation Safety of AESs" by A.B. Alfonso & W. Stregoter.

(6pages)

  • 20, 4/79 English translation (pp. 267-?72) from Atomnaya Encrotya Vol. 40, ho. 4, pp. 227-232. "Lef orm6 tion of en Energy telease Field in a High-)owered Water-Cooled Channel Reactor (RBMK)"

by A.N. Aleksakov. (6 pages)

  • This publication contains COPYRIGHTED MATERIALS. A copy is available for public inspection in the NRC's Public Document Room (PDR).

r u DallasTimes Herald ~ ~"-

May 6, 1986 Di o O Office of Nuclear Reactor Regulation ACT REQUEST

~

Nuclear Regulatory Commission Washington, D.C. 20555 / ,

re FREEDOM of INFORMATION ACT REQUEST Dear Mr. Dentons Your attention is invited to the Freedom of Information Act (5 USC 552), as amended, and to implementing Nuclear, Regulatory Commission instructions and regulations.

Under provisions of the above cited authority and in connection with your responsibilities involving nuclear power plants, operators and materials, it is requested that we be provided with copies of the following documents:

1. Any studies, reports, assessments, evaluations, recommendations or similar written documents in the possession of your office or any office under your jurisdiction pertaining to safety issues, actual or hypothetical, at any of the nine nuclear reactors at Aiken, S.C., Oak Ridge, Tenn., Platteville, Colo., Idaho Falls, Idaho, and Hanford, Wash., which include similar design characteristics to the Chernobyl nuclear power reactors in northwesturn Ukrainian S.S.R.
2. Any summary listing of accidents which have occurred at the nine nuclear reactors listed in No. 1 above. This is not a request for documents pertaining to each accident, but simply any single doc-ument, or computer printout, which lists all accidents in summary forn which may be in your possession.
3. Any assessment of potential contamination, up to and including worst-case scenario, of radiation leakage from one or more of the nine nuclear reactors listed in No. 1 above which may be in your poss-ession.
4. Any assessment prepared wholly or partly by you or in the poss-ession of your of fice of the potential contamination or hazardous effects, whether biological or ecological, national or international in scope, of the Chernobyl accident. This includes tentative or pre.

liminary evaluations and assessments.

5. Any studies, reports, assessments, evaluations or similar writt M en documents in your possession, regardless of source, foreign or do-mestic, pertaining to nuclear reactor capabilities and potential safety hazards of the Soviet Union's nuclear industry in general.

/I 8M8 \Tinies QM7(gM P" l J/J f} u \eu spap.\lirr er i

P

'u ~ ,

Barold R. Denton Director office of Nuclear-Reactor Regulation' Nuclear Regulatory Commission May 6, 1986 Any-studies,, reports, assessments, evaluations or similar writ't-6.

en documents in your possession, regardless of source, foreign or do-mestic, pertaining to nuclear reactor capabilities and potential safe-ty hasards of Soviet nuclear reactorsLmarketed, constructed JaraguaorIplanned and II in other countries,. including but not limited to the reactors at'Cienfuegos, Cuba.

this request ~ includes.all doc-With respect to the Chernobyl accident, time of the accident until the date of proce uments fromIt also the includes NRC-generated documents and' documents from other domestic or f oreign sources, including but not limited to~the request.

International Atomic Energy Agency It also the Swedish andincludes Institute forLthe-do'cuments you may Protection Against Radiation.

have acquired in connection with your responsibilities as an official of the NRC as. well as those you .may have acquired by virtue of your.

interagency task force established to monitor role as a member of the the Chernobyl accident.

If any of the requested documents are it classified in the is requested thatinterest they beof national ~ security or foreign policy, considered for release through a declassification review but that such process not delay release of other unclassified documents em-bodied in this request.

Because of the public interest in the subject, it is requested that this request be given expedited handling.

for reproduction costs or We are willing to provide reimbursementrequest waiver of all fees, under NRC other reasonable fees, butsince the documents are requested in connection with re guidelines, a general circulat-search for articles for the Dallas Times Herald, ion daily newspaper and their release will primarily benefit the gen--

eral public.

If a fee waiver is not granted and fees exceed $25, please first notify the undersigned at 214/760-9152 (office) or 214/

991-5045 Cresidence).

it is further If any documents or portions of documents are withheld, requested that an itemised indez be prepared correlating each with-held document or portion of a document with a speci ed by Vauahn v Rosen, 484 F.2d 820 (D . C . Cir. 1973), cert. denied, 415 U.S. 977 (1974).

sincerely, g

( la % -- --

! JACK H. T R JR.

special rojects/

l- rtaent News D l 2 i

o _ . .. _ _ _ . .. --. ... -

. .; w y[p.,5 .

y$[ V./e ss/4 -

3 0 . .

DESIGN FEATURES OF T8E SOVIET RBMK-1000/CEERNOBYL-4 REACTOR

. A R'eport Prepared For The ADVISORY COMMITTEE ON REACTOR SAFEGUARDS

\ ,,

May 4, 1986 By WALTER MITCHELL, III, P.E.

~~

-h - A-k fp g g .'. $h-3 37 m $4f d 'o

P - . . . . . . _ ~ . _ _= . . . . . _ . . .

p s.

' ~

CONTENTS ,

1.0 INTRODUCTION

. . .. . . . . . 1 2.0 GENERAL DESCRIPTION OF THE PLANT . . . . 4 3.0 REACTOR CORE . . . . . . . . 6 3.1 MODERATOR . . . . . . . . 9 3.2 PRESSURE TUBES . . . . . . . 10

~

3.3 FUEL . . . . . . ,. . . 11 3.4 CONTROL . . . . . . . . . 12 4.0 COOLING SYSTEMS . . . . . . . 13 4.1 REACTOR COOLING SYSTEM . . . . . . 13 4.2 CONTROL-CHANNEL COOLING SYSTEM . . . . 13 4.3 MODERATOR COOLING SYSTEM . . . . . 14 4.4 EMERGENCY COOLING . . . . . . . 14

('~~ ~ 16 5.0 REFUELING . . . . . . . .

6.0 REACTOR PHYSICS . . . . . . . 18 6.1 REACTIVITY CONSIDERATIONS AND CORE LOADINGS. . 18 6.2 STARTUP AND APPROACH TO EQUILIBRIUM . . . 19 BIBLIOGRAPHY l ILLUSTRATIONS l

l

'. J

.t

- - . . . . . . . . . . . ~ . . . . .. .. _.

., c - s.

NOTICE This report was prepared by Walter Mitchell, III as an account of work sponsored by the United states Government. Neither the United States, Walter Mitchell, III, nor any of their employees, .

contractors, subcontractors or their employees, nor any person acting on their behalf (a) makes any warranty or representation, express or implied, with respect to the accuracy, completeness, or usefulness of the information in this report, or (b) assumes any 1

liabilities with respect to the use of, or for damages resulting

\. '.. from the use of, any information disclosed in this report.

6

=

e l

4 l -

?

I

( ,

I t

- - - - . - - - . . . - - - - . . . _ - - - - - - . . ~ . _ - -_ - - ,

" ' - . . ee.. . . . ..

~

.t ,  :-

'* **["0".I:1.' *'EY$$k.- (. .,.9f..

..-f1

,e ... . - . ...-  ;, .

6c 4

..g .. -

p

,. . . , . <. : ; . .. :. ,1, r, ~~ m. , .

'h . *

  • Y..G*kW . Y?:.Wj

- . . .. . . . ,. : . ...<-s ...

.~..u..., . ~ , . .,

.*v i

- . . p.{ %:,.: 6.)W: .. G-L .

..  %- S . y.y. ,e:. )

(- .. . * *

. . ; ,.7.4'.4

. :- !. c. . .. .

.e .* .n. .et m

.. . . . .-*',*y.....

  • / . .M 7. ' 14 l 4 * + '

. * . . *f*,

f - e . . .

I .

d 4

i . .

h 5

h p- .

F p . .

F .

(5 ,/ .

S l

l e

I f .

L-l P

. . g l .

> f I.

L l .

. s

. .- . . ~ . . . . ..t_- . . . _ . _ - .

l

-r t

. l 31-  ;

1.0 INTRODUCTION

\

This report is a compilation of information on design features of the Soviet RBMK-1000 power reactor, a class, represented by operating units at several locations in the Soviet Union. The, purpose of the report is to provide background data on the reactor type to the members of the Advisory Committee on Reactor Safeguards for their use when considering the events that led to the accident at Chernobyl-4.

In attempting to understand' Soviet reactor designs, one seldom has much data on a particular unit -- unless that unit is old and/or the first of a reactor class. Since Chernobyl-4 is neither old nor the first of the RBMK-1000 reactors, little specific information is available. The data given here generally reflect a composite developed from material presented in the open literatures in most cases, the composite was taken from past

      • studies of the reactor type.

The design of the RBMK-1000 was completed in 1969, and the first unit of the type reached initial criticality in late 1973 at the Leningrad Atomic Power Station. By early 1986 at least 14 units were in operation in the Soviet Union, at sites near Leningrad ,

(four units), Kursk (four units), Chernobyl (four units), and Smolensk (two units in operati'on, a third nearing completion, and a fourth scheduled for 1990).

The technology incorp6 rated in chernobyl has its roots in the designs of the earliest soviet plutonium production reactors (1940s). Later production reactors, the First Atomic Power station at Obninsk (1954), the six dual-purpose (plutonium and power production) reactors known as the Siberian, Atomic Power station (1958-1963), the two boiling-nuclear-superheat reactors at l

t Beloyarsk (1964, 1967), and the earlier RBMK reactors all 1

. 1

.t t 1

! contributed to the existing Russian knowledge ~of graphite moderated reactors at the time Chernobyl was designed.

At conferences.and in the literature, the soviets have shown i little reticence in extolling the virtues of their nuclear plants,

be they " water-water" reactors much like U.S. PWRs, or RBMK ,

reactors so unlike our commercial BWRs. In discussing future work, the emphasis in the water-water reactor reports (including those dating back a decade or two) seems to center about potential technological improvements that will improve performance characteristics such as average fuel exposure at discharge. The RBMK list of items deserving additional work seems somewhat i different in emphasis, even when viewed with a stern reminder l that one should not let very-recent events affect his perception.

Put simply, there seems to'be an uncharacterist.ic acknowledgement of safety questions that might be considered unresolved. For

example, the following item in a list of " problems" whose

" successful solution" will "make possible further improvements in

~*

J' 4

  • channel reactors" (RBMK type): "The improvement of safety measures at reactor installations as a way to increase the number of circulation loops and reduce the. diameter of the pipes, including i the development of more effective systems for emergency cooling of
the active zone and the localization of coolant leaks."

l Despite the apparent candor in mentioning things that might need to be done, or improved, there have always been firm statements to the effect that the safety of RBMK reactors is assured by the high

! quality of components and construction, both verified by extensive testing. Strangely at odds with the generally-expressed assurance 1

i that quality levels are high is the following statement by

} Academician N. A. Dolleshal' on the " nuclear class" equipment delivered by manufacturing plants: "It is not possible to state that all is well in this respect." Beyond the question of quality in manufacturing plants, there is the additional consideration of '

(s- quality in the field-assembled plumber's nightmare called RBMK.

l 3 ,

i

}

]

.a t In reviewing the available literature on the Cherbonyl-type resctors, it is practically impossible to select, say, a set of I core design parameters that is internally consistent. This is ,

nothing new, only a reflection of the contradictions apparent in the Soviet nuclear data over the years -- many of them probably caused by rounding-off and lack of up-to-date information by the authors, compounded by difficulties in printing, translation, and i printing again.' An imprecise solution to this problem is to select relatively unambiguous reference-point values and, from tho-o, calculate, confirm, or choose related values. That technique was followed, generally, in determining the numbers given here, though in many cases the available time did not permit a check of any kind.

The author hopes that the ACRS will find the information given in the following pages useful. He also hopes that the Members of the Committee vill view the report in the context of its preparation schedule: one day for research, one day for writing, and one day 4

  • ( j for typing.

e O

i f

I i

%.) ,

g i s L. -

2.0 GENERAL DESCRIPTION OF THE PLANT l

' chernobyl.-4 is (was).a graphite-moderated, boiling-light-water-cooled, vertical-pressure-tube reactor that utilizes low-enriched uranium dioxide fuel.

Cooling water is delivered by main circulating pumps through header / pigtail systems to the bottoms of the reactor fuel channels  ;

(pressure tubes). Entering the reactor at a temperature of 518 F (270 C), the water flows upward around rod-type fuel assemblies, is heated to saturation temperature, is partially evaporated

' ~

[ (average steam content 12 15%), leaves the reactor, and is fed

~

to steam separators. At its rated thermal poser of 3140 Mw, the reactor produces about 540d at/hr of saturated steam at approximately 988 psia and 543 F (284 C).

After separation, the steam is sent to two turbine-generator sets, which produce the unit's rated capacity of 1000 Mv. The

\,,./ * . condensate from the turbines passes through regenerative heat exchangers, is mixed with water from the separators, and is returned to the inlets of the main circulating pumps.

The reactor is, or can be, refueled on-line by a refueling machine located above the top reactor face, as shown in the vertical ~

cross-section given as Fig. 1. It should be noted that Fig. 1 l

o is the classic, generic illustration used in Soviet publications

containing descriptions of any RBMK reactor;. it was taken from an l undated brochure the author received in 1974. Unless identified

[.

by specific plant, the remainder of the illustrations in this report are RBMK-generic.

}

Perspective views of the reactor system'are given in Fig. 2 and Fig. 3, with apologies for the quality of the latter. Figure 4 i gives a plan view of the overall building arrangement at smolensk l l.

and a sketch that illustrates stated differences in layout at the ,

1 i ~,' -

1 l

l-j  ;

- t . )

Kursk and Smolensk stations. The Kursk layout appears to be the same as that at Leningrad, which is consistent with the timing of the stations: Kursk-1 was the third RBMK-lOOO to enter service, .

following-Leningrad-1 and -2 by about two years and one year, respectively. The Smolensk units are relatively new, and could reflect improvements in arrangement. Chernobyl-4 reached initial criticality six months or so after Smolensk-1. .

The reactor itself is placed in a concrete pit with a square

. cross-section 21.6 x 21.6 m and a depth of 25.5 m. The metal support structure for the reactor transfers the weight of the core to the concrete. Shielding and cooling. systems are provided in the areas around the reactor, and the graphite moderator is

~

isolated from the surrounding spaces, as discussed later in this report.

Reactor coolant system components are located in shielded spaces, as would be expected, and these spaces fairly well surround the

'. reactor and the gallery where the refueling machine operates. The

k. / literature reviewed did not contain specific information relating to the construction quality or overall leak-tightness of the reactor building in the regions above and around the refueling f gallery. Old publications typically contained motherhood statements about safety and said that " typical industrial building construction" was adequate for reactor buildings.

e e

~

j -

-~

^ ^

. .. . - - . - ...L. .. : . 7 l

i e ,

A 3.0 REACTOR CORE A consistent set of values for principal parameters-was derived for the RBMK-1000, based on the fuel enrichment (1.787%) specified for the early units in the series. This set of values is given in i

~

the table on the following two pages, with footnotes indicatin,g i some of the differences that accompanied the apparent increase in  !

standard fuel enrichment to 2.04, which yiel'ds a nominal average fuel exposure at discharge of 22,300 Mvd/mtU.

The core is formed by vertical channels arranged on a square pitch of 250 mm. The vertical channels are formed by zirconium-niobium

~

pressure tubes -- fuel channels -- that penetrate the graphite moderator. Each fuel channel contains two stacked fuel assemblies, and each assembly contains 18 fuel rods and a centra,1 support member. The fuel rods consist of uranium dioxide fuel pellets clad in another of the zirconium-niobium alloys developed by the Soviets.

(

  • x ,/ -

Reactor control is achieved by the use of four groups of control rods: radial power shaping rods, automatic regulating rods, scram rods, and axial power shaping rods. The Soviets have studied the potential for augmenting reactivity and power distribution control

~

by fixed and/or burnable poison rods installed in the central ,

support member of each fuel assembly. However, there is no evidence that such techniques.have been imp 1'emented, and it seems t unlikely that they would be used extensively due to the associated penalty in dischar.ge fuel burnup.

The pages following the table of data give more detailed I descriptions of some of the design features of the principal core j components.

i (

\_/ ,

~ ^~

^~

4

t .

Table 111-1 RBMK-1000 REACTOR DATA j

Type ..

Channel-type BWR ,

Thermal Power, W 3140 Core (Equilibrium)

Active height, a 6.94 ,

Active diameter, a 11.8 Total number of channels in core 1884*-

. Number of fuel channels 16g3 Number of sensor channels in core 12

. Control .

Rods in 179 channels

  • Power density, kw/ liter 4.14 Refueling On-line Moderator Materfal Graphite

! Density,g/cm3 1.67 Average temperature. 'C/*F 600/1112 Process tube holes Diameter, m 91 Square pitch, m 250 Process Tubes

.( Material Ir-2Wb

( .../ -

Dimensions, m ID = 80, 00 = 88 Average temperature. 'C/*F 300/572 Coolant Material

~

Boiling light water Nominal pressure, psia 988 Reactor inlet temperature. *C/*F 270/518 284/543 Reactor outlet tempergture 'C/*F 0.516 Average density, g/cm

~

e

  • These figures are for the initial RBMK-1000 design, for which a feed enrich-ment of 1.787% was specified. Later reactors in the RBMK-1000 series (about
i. the sixth and subsequent units) utilize a feed enrichment of 2.05. These t later units have 211 control-rod channels and 1661 fuel channels, at least i during the approach to equilibrium (and probably throughout their lifetimes).

iDedicated channels on regular lattice positions. Additional sensors are lo-cated in the central support tubes of 270 fuel assemblies.

l (. .

+

r .

8 Table III-1 (Continued)

Fuel Assembly Number in each fuel channel 2, stacked .

Fuel Rod Number per assembly 18 (plus unfueled support rod)

Cladding .

Material Zr-INb Dimensions, um ID = 11.7. 00 = 13.5 Average temperature, 'C/*F , 291/555 Fuel Feed material 1.787% enriched 002

  • Average density, g/cm3 9.814t Pellet diameter, um 11.5 .

-Average temperature. 'C/*F 546/1014 Burnup, nominal, Mwd /mtU 18,500 Core loading, utU 192 Control Rods Number and type - 179 total *

- (RR 125 Radial power 12 Automatic shaping regulating (AR))

21 Scram (AZ) 21 Axial power shaping (USP)

( !'.

. .. Poison material Boron carbide Features Rods formed of articulated sections; RR, AZ, and USP rods have " follower" sections to displace water in core when rods are withdrawn.

\

9

  • These figures are for 'the initial RBMK-1000 design, for which a feed enrich-ment of 1.787% was specified. Later reactors in the RBMK-1000 series (about the sixth and subsequent units) utilize a feed enrichment of 2.05. These -

later units have 211 control-rod channels and 1661 fuel channels, at least during the approach to equilibrium (and probably throughout their lifetimes).

i $meared contained within the volume defined by the inside di- l

, density of UO2 I l

i

( _ ,/ ameter of the fuel cladding and the active height of the core.

I oQo

, 't .

p 3.1 MODERATOR The constituent assemblies of the moderator are graphite with a ,

density of 1.67 g/cc. This graphite density reflects an intentional reduction from the 1.73 g/cc material in the first unit of the Leningrad station, even though there is a reactivi,ty penalty associated with the density reduction. Leningrad-2 and subsequent units apparently use the lower-density material as one means of reducing the positive steam void coefficient of reactivity. (The change in fuel enrichment from 1.7874 to 2.0% was prompted primarily,by the same desire, and not to obtain greater discharge fuel burnups.)

The moderator is contained in a sealed space formed by a

" cylinder" of metal and the plates of the upper and lower

" assembled steel sections". The space and its boundaries can be determined by looking carefully at the details of Fig. 5.

b

  • \- - *
  • The moderator space is filled with a mixture of helium and nitrogen (404/604 by mass) to prevent oxidation of the graphite

.and to improve heat transfer from the graphite to the pressure

! tubes, which are the dominant heat sink for the moderator. Leakage

. of the moderator blanket gas is limited by filling the spaces surrounding the moderatori" vessel" with nitrogen under a pressure ,

l exceeding that of the helium-nitrogen blanket gas by 20-120 mm Hg.

Average graphite temperature at full power is approximately 600 C (1112 F), a value consistent with reported maximum values of E60 C (stabilized maximum) a'nd 750 C (initial maximus), and with a calculated value of.660 C (for a slightly different blanket-gas mixture and gn inco8 rect assumption regarding the interface

'between the Graphite and the pressure tubes).

i - Energy deposited in the graphite is reported to be 5% or 6% of the core power, figures that look reasonable -- if a bit on the low side. The removal of this heat is discussed in a 1,ater section.

I 3.2 PRESSURE TUBES I '

The vertical pressure tubes (fuel channels) that penetrate the graphite moderator and contain the reactor fuel assemblies have an outside diameter of 88 mm and a vall thickness of 4 mm. They are illustrated by Fig. 6, which is a vertical section through the, full height of the fuel channel assembly.

Each fuel channel is fabricated of two materials. In the core I region, the tubes are the zirconium - 2.5 niobium alloy that has I been the subject of Soviet development efforts for more than 20 years. Above and below the core region, the . tubes are stainless

~

steel. The Soviet development program on the transition joint between the zirconium alloy and the stainless steel began in 1965, and descriptions of the need for the program make it clear that

- the Soviets were aware of the development efforts elsewhere on a transition joint between basically the same materials (at least one U.S. effort was underway in the late 1950s). The solution

- - \_ *

. adopted by the Soviets, the basis of which is diffusion velding, is illustrated by Fig. 7.

At the top and bottom of the reactor, the principal horizontal F steel structures are fitted with vertical steel sleeves that house the upper and lower portions of the fuel channels. The channel is,

, welded to the top housing sleeve at the point indicated by the "4" i, callout in Fig. 6, while the attachment at the bottom housing sleeve consists of a welded-in bellows, indicated by'callout "12".

h The bellows, which accomodates differential thermal expansion, is ii backed-up by a " stuffing-box seal", item 13 in Fig. 6. The

, service life of the fuel channel is estimated to be 25-30 years (reactor lifetime is said to be 30 years), and the channel is said 3

l to be replaceable. Replacement 'is accomplished at shutdown, with remote cutting, welding, and x-ray flaw detection equipment at the top sleeve and remote cutting and welding equipment at the bottom sleeve. The x-ray flaw detection story is hard to believe.

s N . ',

3.3 FUEL Each fuel" channel in the RBMK reactor core contains two stacked fuel assemblies, as shown in Fig. 8. The fuel length in each of the two assemblies is approximately 3.5 m, and the assemblies are joined. The gap between assemblies at the joint is about 20 mm.

Each fuel assembly consists of 18 fuel rods and a central support tube, with grids providing rod spacing and the connections between the rods and the central support.

The fuel cladding is Er-1Nb, another of.the Soviet alloys with a

- long development history; it'is basically theJRussian Zircaloy.

- The central support tube is also a zirconium alloy, composition unspecified, but certainly either the INb or the 2.5Nb material.

The grids that provide fuel-rod spacing and connections to the support tube are stainless steel.

The fuel rods have an outside diameter of 13.5 mm and an inside

- . diameter of 11.7 mm (35-mil vall). They contain 2.0%-enriched I uranium dioxide pellets 11.5 mm in diameter (4-mil gap between the

, pellets and the cladding). The central support tube has an CD of 15 mm and a wall thickness of 1.25 mm (50 mils). Either a g

carrier (structural) rod 12 mm in diameter or a 12x2.5-mm pipe j passes through the central support tube. t i

The fuei density has been reported to be "up to 10.5 g/cc" and

"not less than 10.5 g/cc." The latter figure may be correct, but

$ for years the Soviets seemed to have difficulty producing high-density pellets. "~ .

( Nominal loading for the 2.04-enriched core is approximately 188 '

atU. Average temperature of the fuel is about 546 C (1014 F), and

]

4 the average fuel exposure at discharge is 22,300 Mwd /stU. During h-i the early years of the reactor's life, the discharge fuel burnup is lower, as discussed in Section 6.2, Startup and Approach to ,

Equillibrium. . .

-M- _ ._ ___ _. _ _ _ _

e , ,

^

, 3.4 CONTROL

'r The react"or control system contains automatic regulating rods, scram rods, radial-power-sh' aping rods, and axial-power-shaping j rods. The axial-power-shaping rods are withdrawn from the core downwards, and the other rods are withdrawn upwards. Movement of the rods is said to be accomplished by servodrives installed i

directly in the control-rod channels.

The general arrangement of an RBMK control rod is shown in Fig. l

9. The rods are formed of articulated. sections and are equipped with foi, lowers; the' followers displace waterJin the core when the ,

rods are withdrawn. The rods move in channels made of the \

l' 2r-2.5Nb alloy used for the fuel channelst at 88 mm, the outside diameters of the two kinds of channels are the same., The control-rod channels have thinner, 3-me walls.

i 8

j The rods are built up from standard absorber elements with articulated joints. In each element a 65x7.5 mm boron carbide  !

! sleeve is contained in a leak-tight annulus formed by a 70x2 na t outer tube and a 50x2 mm inner tube, both made of aluminum alloy.

[

s h-s The axial-power-shaping rods contain three of the standard absorber elements and have an overall length of 3050 mm, while the.

l a

other rods are formed of six elements, giving an overall length of ,

i 6170 mm.

j t

The nuclear instrumentation system includes self-powered neutron i detectors in groups of seven for vertical monitoring of the' power

! distribution. These detectors are located in 12 channels of the same design as the control-rod channels, distributed over the l central region of the core. For radial monitoring, self-powered i

detectors are mounted in central thimbles of 130, fuel assemblies.

1 5 - Four reflector channels adjacent to the core contain fission

(, chambers to monitor the neutron flux at startup.

B ,

i

' -M- - _ _ _ _ . _ _ _ _ __ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _

  • a n.
  • {

(- 4.0 COOLING SYSTEMS 4.1 REACT 6R COOLING SYSTEM .

.The general components of the reactor cooling system were outlined earlier, when the header / pigtail systems for delivering coolant to i

the individual pressure tubes were mentioned, Though the plumbing required for such systems is extremely complex, there are advantages -- including the ability to individually control the coolant flow to each fuel channel, which could result, theoretically, in perfect matching of the channel power and the channel gooling. ,

I In the RBMK reactors, a shutoff-regulating valve (Fig. 10) provides flow-control and isolation functions for each fuel channel. The valves are installed in the pigtails, near the headers, and are operated remotely through the use of shaft extensions. Projected lifetime of the valves is 50,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />,

(,J** '

so there will be a lot of valve replacement going on in the reactor cooling system.

The inlet pigtails have an outside diameter of 57 na and a wall thickness of 3.5 mm, while the outlet pigtails are 76x4 mm.

4.2 CONTROL-CHANNEL COOLING SYSTEM

~

The control-rod channels share a cooling-water system with the graphite reflector (see below). Flow direction is downward in the control channels, and'the water temperatures are maintained at low values (40-60 C) in deference to the aluminum alloy used in the control rods.

i i

1

'o ,

l

,. . . i 1 ..

[ 4.3 MODERATOR COOLING SYSTEM Heat is removed from the moderator graphite by (principally) .

transfer to the reactor cooling system, through the fuel channel walls. The RBMK design uses a series of stacked, split, graphite rings, illustrated by Fig.11, to improve the heat transfer from the surface of the graphite fuel-channe.1-hole to the outer surface of the 3r-2.5Nb fuel channel. i l

The control-rod channels also provide moderator cooling, and they

! are equipped with the same 20-mm-high graphite split rings that are placed around the fuel channels. .

The reflector cooling system, common with the control-rod cooling l

system except for the distribution pigtails, provides 156 cooling channels in the peripheral row of graphite columns.

4.4 EMERGENCY COOLING

~.

l ~.  :

There is an independent, emergency fuel cooling system for the reactor. It is said to consist of two subsystems a main system having a water storage tank, and a subsys' tem for long-term cooling, utilizing special pumps and water stored in tanks. In addition, it has been stated that feedwater can be routed to a .

I discharge header, presumably for the purpose.of being pumped, opposite to the norma 1 flow direction, back into the fuel channels. -

t At least one Soviet st'udy investigated the division of large compartments containing rse.ctor cooling system components'into smaller bays, with check valves installed in the partitions that form the bays. The purpose was not clear, unless the system was used with what looks like a pressure-suppression, system also studied by the same scientific institutes.

t mRA-

2 .

The pressure-suppression possibility is interesting, in that it

(

was never mentioned or illustrated in publications on the ea'rly reactors.in the RBMK series. The typical, or generic, RBMK drawing, given here as Fig. 1, shows no suppression pool (" bubbler basin" or " bubbler pond" in the Soviet study mentioned above and

< in illustrations to be cited in a moment), nor do any versions of that drawing, regardless of the amount of detail or the number of identified features.

Now refer to Fig. 12, a vertical section through the reactor

building and turbine hall at one of the Smolensk units. Note the differences between this figure and Fig. 1, in the region beneath l

the reac' tor and the coolant pumps. On the Smolensk drawing,

, features 16 and 17 are, respectively, " accident containment valves" and " bubbler pond."

j

! In contrast to the differences in drawings for the RBMK-1000 reactors, it seems that all depictions of the RBMKP-2400, the f(\_/ *

. 2400-Mw(e) nuclear superheat plant being studied by the Soviets, I

show the bubbler pond (see Fig. 13).

~

It is difficult to find much information on emergency fuel cooling f

systems and procedures if there is any mention of emergency cooling provisions for the graphite moderator, that mention is not conspicuous, as one would expect it to be if it existed.

l-l t

([- .

. o

, 5.0 REFUELING

\

The reacfors have on-line refueling capability, although refueling was accomplished at shutdown in the early stages of operation of at least the first unit in the. series (Leningrad-1). The sequence of operations employed when refueling on line is as follows.

The refueling machine is readied for refueling operations (charged with water that it will use later, loaded with a fresh fuel assembly).

The operator instructs that a specific fuel c'hannel be prepared for recharging. The protective plug is removed from the channel and the cable of a gamma detector is disconnected from the assembly plug. (These operations are done manually by workers in the refueling gallery, and the protective plug mentioned above is what appears to be a square cover in the numerous photos of the reactor top face.)

The refueling machine moves automatically to the lattice position that has been prepared by the workers, the machine nozzle is joined to the top-end closure of the fuel channel, and a high-pressure seal effected. Pressure in the refueling machine is l raised to the pressure in the fuel channel, and the channel is .

unsealed. Water from the refueling machine (.at 30 C) is pumped at pressures greater than 1000 psi into the fuel channel.

The refueling-mac' hine grab latches to the top of the fuel assembly l

and withdraws the column of fuel about 7.5 meters, to what is called a cooling zone (sounds as though the fuel column is lifted to an elevation in the fuel channel that is just above the active core region). The fuel column is held in this position for 10 minutes, with cool water flowing down over it at.a rate of 0.5 to 1.0 cubic meters per hour.

> U '

l -

I

- -_ m

.The spent fuel is raised and stored in the refueling machine, clearances in the now-empty fuel channel are checked with a gauge, and the fr'esh fuel assembly is lowered into position in the core.

~

The procedures followed to attach the machine to the channel and open the channel are reversed, the seal of the fuel channel is checked, and the refueling machine proceeds to a spent fuel .

receiving area,.where it unloads the column of spent fuel it removed from the reactor.

A simple cross-section of the refueling machine is given as Fig.

14, the grab that attaches to the fuel column is shown in Fig.

15, and the top closure of the fuel channel is illustrated by the

? cross-section given in Fig. 16.

At shutdown, a cooled reactor can be recharged by the refueling machine, with simplified operations, or by workers using other equipment located in the refueling gallery.

v.(;.=).

s le .

,0 i -

1 d

O r

1 l,

. N,-] .

1 I

i

-m.-~_-_,.-

.. - . j 1

6.0 REACTOR PHYSICS In the pa'st, the capability of the Soviets to perform reactor ,

physics calculations seemed to leave something to be desired.

l This seeming lack of sophistication probably stemmed from a lack of computer capability. In the RBMK reactors, with their six Df materials and components, calculations are not easy. There seems to have been some catching-up on the part of the Soviets.

RBMK values apparently are derived from two-dimensional calculations based on a 16-channel periodicity cell, with coupled thermal-bydraulic feedback, thereby reflecting the spatial

distribution of steam void and channel power.

4 6.1 REACTIVITY CONSIDERATIONS AND CORE LOADINGS ,

i During normal operation in both the approach to equilibrium and the equilibrium cycle, a small margin of reactivity, held down by

'('2'

- '. control rods, is reserved for power maneuvering and operational flexibility. The Soviets have investigated the consequences of 4 different amounts of operating reactivity reserve, and have suggested that 1% is the reserve normally used. This appears to be

somewhat low, and a reserve twice that would not be unusual.

1 The steam void coefficient of reactivity was. mentioned earlier, when it was stated that the principal reason for the change from an initial fuel enrichment of 1.787% to 2.0% was.to reduce the value of this coe'fficient. Above 2.0% enrichment, the coef*icient becomes negative, resulting in greater stability of reactor operation. A similar reduction in the steam void reactivity coefficient occurs with increasing reactor power, as seen in the negative coefficient, at 1.8% enrichment, for the RBMK-1500, a souped-up, higher-channel-power RBMK-1000. ,

L' -

9 1 _gg.

t The initial fuel loading for the reactor consists of about 1450 fuel assemblies containing approximately 165 metric tons of enriched uranium. ,

The initial cycle extends over a period greater than four years, requiring about 1340 fuel assemblies containing some 150 metric tons of enriched uranium. The average discharge burnup of this fuel is slightly less than,20,00d Mwd /mtU.

on the equilibrium cycle, with the reactor operating at 80%

capacity factor, the number of fuel assemblies required annually

~

is 369. The annual requirement for enriched uranium is about 40 metric tons, and the average discharge burnup'is 22,300 Mvd/atU.

6.2 STARTUP AND APPROACH TO EQUILIBRIUM Startup of the RBMK reactors is a difficult and time-consuming

. process, for the operating conditions and number of fuel

,/ *

  • assemblies in the core are constantly changing. Procedures are adapted to each reactor on the basis of accumulated data on that reactor as the initial cycle proceeds.

Most Soviet reports state that full-power operation is reached f

[

within 9 to 12 months after startup, though the length of the ,

h " transitional period" is also given as 5-6 years. If full power is reached in 9 to 12 months, either operation at that level is not 4

l. continued or necessary shutdowns 1,imit the plant espacity factor during, at least,i the first four years. It ' appears that the reactor operates at-less than full capacity over the first four i, years or so, during which time all of the fuel and absorbers initially loaded have been sequentially replaced by new fuel assemblies and a full core loading has been reached with distributed burnups approximating squilibrium conditions.

$.x/ ,

chernobyl-4 achieved initial criticality on December 14, 1983. If

  1. the approach to equilibrium in RBMK reactors continues for the time periods mentioned above, chernobyl-4 was still in its ,

approach cycle. j i

The Soviets investigated a number of methods of controlling power

. peaking and reactivity in the initial cycle (s), apparently selecting a met' hod that uses uniform equilibrium-cycle enrichment (2.0%) together with less than a full-core charge of fuel assemblies, reduced power levels, and extra absorbers distributed throughout the core. During the approach to equilibrium, the absorbers are gradually replaced by fuel assemblies, as needed, to control power peaking and to provide the necessary reactivity.

This method necessitates the removal of some fuel assemblies from the core with burnups substantially less than the nominal design value -- possibly as low as 12,000 Mwd /mtU.

(:. }- .

A e

9 l

l .

i r

p F

N,.

f

BIBLIOGRAPHY

  • M. A. Dollethal' and I. Ya. Yemel'yanov, Channel Nuclear Energy Reactor

~

. (Translation), JPRS L/10150 (1 December 1981).

B. A. Semenov, Nuclear power in the Soviet Union. IAEA Bulletin, 25(2):47-59 (June 1983). '

V. S. Romanenko and A. V. Krayushkin, Physical Characteristics of an RBMK l Reactor in the Transitional Period (Translation'). Atomnaya Energiya, 53(6):367-373 (December 1982).

I Yu. I. Mityaev and V. K. Vikulov, Cassette Permutation to Equalize the Ener )

' Distribution and Improve the Fuel Cycle of- the RBE Reactor (Translation ,  !

Atomnaya Energiya, 52(4):231-235 (April 1982). l I. Ya. Emel'yanov et al., Increasin l

the RBMK-1000 Reactor (Translation)g , Atomnaya Energiya, the Efficiency 46(3):139-141 of',(March Uranium Utiliz 1979).

V. G. Aden et al., Fuel Elements of the R8MK-1000 Reactor (Translation), J Atomnaya Energiya, 43(4):235-239(October 1977). j I. Ya. Emel'yanov et al., Power Distribution Monitoring and Control for a RBMK

,  ; Reactor (Translation),AtomnayaEnergiya, 48(6):360-365 (June 1980).

. A. P. Sirotkin, Conference on the Fifth Anniversary of the Commissioning of

- Leningrad Nuclear Power Station (Translation) Atomnaya Energiya, 46(5):364-365 (May 1979).

i P. M. Kamanin et al., Measurements of Spectral Indices in Uniform RBE Reactor  ;

' Lattices for Various Channel to Graphite Temperat'ure Gradients (Translation). I Atomnaya Energiya, 50(3):176-181 (March 1981).- l i

I K. Polushkin The Nuclear Hercules (Translation), Nauka I Zhirn', No.11, pp.

j 44-52 (November 1980).

L. M. Voronin, Experience in Starting up and Mastering the Rated Capacity of Power Generatin9 Units with RBMK-1000 Reactors (Translation). Elektricheskiye Stantsi1, No.1, pp 10-15 (1979).

1

! M. A. Dollerhal' and I. Ya. Emel'yanov, Experience in the Construction of Large Power Reactors in the USSR (Translation) Atomnaya Energiya, 40(2):117-126 (February 1976).

Atomnaya The Leningrad AES Imeni V. I. Lenin (Translation) l' N. F. Lukonin):220-223 Energiya. 48(4 (April 1980).

I I k'" ,

  • Names and publications have been spelled exactly as they appear on the articles.

l .

i

-B f

~ .. . -

. . - , . . . .~ ...--....

l I'

l V. Dubrovsky, et al., " Construction of Nuclear Power Plants", Mir Publishers, Moscow, 1981. .

" Reactor RBM-K",-Brochure, USSR, undated.

N. A. Dollezhal', Graphite-Water Steam-Generating Reactor in the USSR, " Nuclear Energy", 20(1):385-390 (October 1981).

Leningrad Atomic Power Plant (Translation), excerpt from the book "Atomnaya Energetika XX Let", Atomizdat, 1974.

Leonard Konstantinov, Commercial Reactors of the USSR, Lecture 2.2.13, IAEA Interregional Training Course on Nuclear Power Plant

. Construction and operations. Management,' November 2, 1976.

~

Chernobyl-4 Goes Critical, " Nuclear Europe", 1/1984:48.

V.-Y. Doroshchuk, Radiation Safety at Atomic Power Plants with Water-Cooled Reactors (Translation), Chapter 7 from the book "Yadernyya Reaktory na Wlektrostantsiyakh", Atomizdat, 1977.

N. A. Dollezhal' and I. Ya. Emel'yanov, Experience With the Construction of Large Power Reactors in the USSR (Translation),

j "Atonnaya Energiya", 40(2):117-126 (February 1976).

(ud

  • Gloria Duffy, Soviet Nuclear Energy: Domestic and International Policies, The Rand Corporation, Report R-2362-DOE, December 1979.

I. Ya. Emel'yanov, et al., Physical Startup of the RBMK-Reactor of the Second Unit of the V. I. Lenin Nuclea'r Power Station,

. Leningrad (Translation), "Atomnaya Energiya", 40(2):127-132 (February, 1976).

k "May the Atom...", A Report of the U. 5. Atomic Energy Commission Delegation to the U.S.S.R., August 1971, USAEC Report TID-26162,

~

l October 1972.

~~~~

A. M I 3etros'yants, et al., The Leningrad Nuclear Power Station and the outlook for Channel Type BWR's (Translation), "Atonnaya

~

j i Energiya", 31(4):333-343 (October 1971).

A. P. Aleksandrov and N. A. Dollezhal', Development of Uranium-Graphite Channel Reactors in the USSR (Translation),

"Atonnaya Energiya", 43(5):337-343 (November 1977).

I l

i k ~. .

, -B b- ,

l t

I-reactor: 2-water hpellnes; J-steam. .

water pipelines; 4-leading snachine; J-separator drum; $-main circulation pump i

' E

_____ - -______. l

~ ,

( ;4 f?m. M ;l l .

aw .u msw i l  : t'

  • s E .J L l

~

N E

\ _. E m N k

( .mn .t

\

.f Pe,i 4

3

[ i.'

g 7 .. ., m; - g' mamams;g' .pgmm/ . , ,. ,yg 4 .  : N V L

, . L, .,

I

.%, M $i Q

.... L. d@j AO I,

i L!

% 5F N

~

N SI i t

) ]' l[ W"MM . .

, . . . ,, _ . - . .s

' ~ :, #j' DAWN.

j,

'hb f 1 i 5 E e-- -

a g/ ., l, Mi h ky NN

~- -

.. i w  !

q i

-- u-2 e_ .. -= .< '

l b ,, b M M .

i 6 4

! I l

k, hlIIll33N l  !

y, I

EONIIN isl

.- *[

  1. ; I j N, a ddidhiik i ,

le-@}  ! >%1 h i jf.)

i J 8 i

.u,..

u

. : ~ , , ra -

g

. . ., . ...w

/ v O

.-. f r - L~

r" ' -- - ~*^- ~ n v .- ?

pr_p. <.-=~- ,- -- i l l' / /

y t I l

k '

Fig. 1 Vertical Section of the RBMK-1000 Reactor.

l N.. - .

1 1

1 -. . - - . . - _ - - . . , - _ . . - . . .

b  ! t Reester .

NN  :=,;: -

\\ llll:::,:::::" -

.;4a w

NN 3

=a t: == =- -

\ f, l.:[  !!E """"

8 hs I I ,

l

. -:. *e Ea _

2 P'll ..

p *.S 4. ,;,

.5 f ll ,

p c-97)lj 0$& f u mm . '

4 r

!! 1 ; i

, m ..

)

I M

i  ! '

A

__ } >

Fig. 2 Perspective View of the RBMK-1000 Reactor.

.P ', ,

I I L , I, (

I l i E

Q;Jdj i" 1 9 i/

j$h7  %. ij s ed*'i

{, j

,S / Ql@Il% i. r','

g ,

b.lj L..h.y fN({:

l l

'I*deselg:-3 ":

i  :  !

'i . ..

h,q i;.  %

l

'9.;.1 p jl,.

s '. y,j  !

S .i h..' .p3 j j fj i e  ! '

f E.'-

'i.i. E! $ s.

t i .' 'j ' -

i *h I _' ,s , i .f ' . m., v fu, i  !

j ra )

! Y '

l~'lf 5 ri . - k4l q{5.t1 ..w ..: f i

~

l 3

) . ,

l

-:f., ..tf.n.. !i%;'$ '

r- +- l .

y fq f

9i!'I . Y I;- .s. , M h d E. d .

l '

i ,

M

~

'$-[ 5%h

,i M h

_ _ -___. Mf" ;;{4 ew .. '

.g;.y.p @ - - -= 4 .**>. * [-*j

-', " tmiu g ,]

,4({,' W hg

4Mg sl9,n ... . ;-l.4 7

e( '3. !h T

-.}R-7  %

R pa a

gg;

, l

- 3'

  • ".,. s .. -

e___ ._  ! & 'I

  • i Fig. 3 Artist's Rendition of the RBMK-1000 Reactor.

l l

l

a-JiadB

! Aset

. -- RootA F JinctE

\

\

or ,

4F Blnd 7 I

\

l a .-

s \ .#.

g yv

Y 91 Layout of the first stages at (e) Ku
vk and (6) Smolensk

'l

~  !

1

( )

r,.

, g i 8ad bEC4 s b ,

H~oooo f g acr=rtie{ F 'oooo um

~

l p p- m o v/JJ ,, I i 1 a ""

N I 5

~

N l

~~

[

l ic i

-.E: f"oooo00DD'Tr10

., i as eaoooo'll k/

a I\ _

y 34 -

-'Hf'~ v 1: ___..i.,- :

,,i i  ;

i

-g .

j :m nam ( - . W _ W .DI w aar

, em . mar i m aar

! Jertiss K Arrlar R / AsemarE M(at/

j As# esat amis l Plaa of the mala building at Smolensk I

i -

3

/ Fig. 4 Plan View of the Main Building at Smolensk and the j .- -

Layout of the First Stages at (a) Kursk and (b).Smolensk.

1 -

4 lb

) '

k -. - . - - _ - - _ . - . . _ _ . - . - _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

I

/

i-

?.

3 i

,...,.,_:--w .r .-x. u r w. . ~ . . r.. . ex m .. ,,. ., . 7 -

. ' . .n_ ,,, f w

r

e. . ...

,a w .a

. ,ig H d Jr .: e"

.a , ,

~

,u ,

e ig i

..g

%=

k. _.h 9E!!ib.

__ T_.:.: .N_' "-"4 "t it , ;dn,ii

.";$. i.l. _t. ,

i :: fi . .

-F_ G ,,.

I b_ bh'8 [. , *.! dj '* p kNhf

. ?g.e.:

a:

. e;. . ~.

dd E 0, d e. A w e' *:

  • O
  • l: x*:::

. N.Jt1r  !.:.  !. : . cg 3.. .. .:ii. .q r b

b ." .

-s l W' .: R. :.:ld $.,.'.#.'..:2.:{

W'.;,'.  : 9 J5 h i ,s

c. [ 37.r. ,b v,.. e. .

..L 1::

h. - v.(9 1s . ,. ;-

w . .. ,

},- ,..-

. ve g '

, , ,v .

. v. . , , ,

. r,-, '

6  ; ...:

, , .- :g:

',z

' . . .n

,- m 1 em w

, , w... .., .

, v .,, ,

,4 n

4. :. ,

n

,w -

.,. w>, . ,. , ., ,

.. e y: 2:

n.r

..o ,, .-v a' v, . .

t.... :. , , , , .

,b .,

, , ..i

, y a v.-

IC .v l.., y ,,t.1,,,,,,,, .... --

..:n

- i .

g

i. s. ..

l,,lll m iN.I b,l La Ill i '. ' }.;:

'. . o [l !.!I

, ',1

. Illu.s.

.llll, I f, ilia. .

?

p

. t .
:. .. 3 ,d ,;

m .vaa. i  ;, .s i F i - -

7t- h-.-

,,1 t a., .. . - .<.~.

m.i. * <. e % l'.y 4,, ,

.z.. :,i.a .%LsI 3o:y , ,

g.w i:'<.9 .>s i .m .

r i , .

.;;sy m

gr. .::..  : , o .

e... #. 3_

.. 1, n , ,,

J h.. m. . . ,-- r .*J.ii.h...<.G..

1 e :...

i:;;i.

. e:.;,.C f . e.

,.e *. .*e . . i i..

. . . *.....* <.. ;:.. :..:.r. . . ...

.. v.

  • s. s:. .. ...;.. u.r.:.'. :.:,. . . . .. . . .::,:3.s,:%: ?::%.. . .%:

.!: . M :.'.. . : .s .* *.:.* 4.,,p:.;;' ,.*. '. % .;l.%.J.V., . .,; .

  • ; .e . .
o- ,

s

  • f Cross sectionsiview of an RBMH 1000 reactor station building (reactor shaft)

-- - s geen seeme: s-eesanarr emnerme; s.-aren-bertam earpentanne eement. Week: s-serpensanne; s-enne: e-water a

3 ._ .

e I

i i

1 6

1 6

'. ( Fig. 5 Vertical Section of the Central Portion of 1

( .. the RBMK-1000 Reactor Building, showing Core Region. -

b 4

L

~

}

~

l &y.

li y ,:

f: .?

7 l ,

I s! >u,  :  :

l .

m;R e, l 0it ll'9l <.

l t' 3 :5 ll.f-:

4j;  ;; .;,, 5

,,,2 il /"i E #! ..  ! El r  !

! O l -l !l dl) amory' l

t:

'! I s.

- pie mg ,

l l fl l l t

Uh i g "

l j

  1. N b  : ( i  !

, t P'

. L._./ . . ,  !  !* j

!E Sj I '#

y:

A

,:*,.C.s.

2.:.:9.'

s

'. 2 j

\ %G , T:g, I' ' '

g~

t l h..i. .

T.

f 23 jI2 - -

$ k f

. ,. 1 -

[

h.N u s _;  :?

ReYS

1. steam-water mixture 2. Water l
  • s' Fig. 6 Vertical Section through the Fuel Channel.

( .

1--Plug 2--Upper reactor section 3--Support fillet [ 4--Welded seam l 8--Fuel Assembly 5--Fuel-assembly suspension: 6--Housing 7--Plug cap

[

10--Lower reactor sections 12--Bellows asse ably; 13--Stuffing-box seal

..,,-.---r,y- - _ . . - _ _ _ _ - _ . - - - _ - . , _ . . . _ , _ , , , .._..._-,-.-____.--,,--_-_-.__e,,_.-..---..-w_.--_ _

t

( .

P d

~

DIFFUSION ARGON-SHIELDED WELD ELECTRON ARC WELD . BEAM WELD

! f .,. . .... . ,..... . x f u y y u I ._.. .

I

, I *

..(--.'.. m

.. o.s

\ \ w .. \

STEEL g.

STEEL

'I 4 t I OKhlSN10T I 1Kh17N2 Ze aDoy-staWeseeted joins. L OKh18N1&T sesel

[ sube. 2. Bimetal sleeve. 3. Er-2J% Nb doy dpple.

i; 2 4.Ze-2.5% Nb alley anbe. ,

~

1  !

l. ,n

. 4

[

Fig. 7 The Zirconium Alloy - Stainless Steel Transition Joint.

( ... .

1

( .- - - . - _ - - . _ _ _ _ _ _ _ _ _ . _ _ __ _ _ _ _ _ _ _ _ _ _ _ __ _ _

/

A B-B

. m ist .

1: oe iTI 1 .t. # '

p.g .

" ~

3( 01 .

  • 7 Ih, 1 /

N .

- m .hs ,,, ., $=K 1

u /

. 4 x Q.,

.f -

x .

if }A

.W. l T

f1E!Isib ( p.y

[

  • M 2 l' t , MW\ r 1 g

. .i r Mh 1 .

e l I fI, lI-I ,<

-l l Dimensions in ami.

, s ,

r -

Fuel rod r {

j r 1.

/. 2. Central support I.

3

/

Fig. 8 RBMK Fuel Assembly Arrangement, Showing the

' Loading for One Fuel Channel in the Reactor Core..

? -

4

(

(. -

-- .1 _

. 5 L

- 2 .

- I -

4 I

). - . . ,

)

e/, -

Absorbing stod: 1--cables 2-204 3--absorbing section l:

4--telescopic extension 5--displacer section l'

Vertical Section of a Control Red.

( Fig. 9

q

.. . . i t

li} $ .

f

.[- '

. .E ' ' u. I g

sg '

A N * -

N%hl 4

/y#

l l ., ( '

.d

k. E sp hj dl E d  !

"fi == .

sly " r l

- d --

? _

NE n ::lE l #*

e; Jm

, qhga.,. A73 4 a

.* , ,==

" ,, aW kRRZRlR 99'RRRR +

l l ,,,

M

  • ~ -- e w l .lj l h h .

fy t m;  : .

l E3 l

'A4 f

{i] s '

un -

\" ~

u j

g .

I shutoff-Regulating valves 1--indicator 2--indicator screws 3--drives 4--drive shanks 5--threaded sleever 6--connectors L 7--rings C-shaft: 9-sleever 10-gaskets ll-bellows: 12 -

housing: 13-throttle valves 14--and piece 15-throttle valve ,

seat 16--group collector p .

1

( Fig. 10 Fuel-Channel Flow Control Valve.

( .

lI h

c

l' k

5

> s;ay c

~

f.k' . M '

r F: l  !% . 2 fd Tussaam4 i M 8 s

j$,  : '

'-; _ W/4 '

. -4

& $91 -

3 "d'*  ;

199f Q'7' i , ,

e N

j g

h.#y' e

l8 Presaw sube 6: graphite staddlag.1.Er-2.5% Nb .

}

mbe. 2. Graphite ring-outer. 3. Graphite d=g Scx. 4. Graph-

~

li lee. .

9 .

O 4

n,. u .....

( ..-e _,... .. ,ob. ,,... co . .u. ,u....

4

.. . .. ~ .. .....~..a . .

e .. .

~

(

\

c I

vwN '

t.

N.

n x n  ;

a M \

I N 4 an .

  • ?
  • ~ L, d=. . W. . ". 'd- . -2 . .

\

m

,, wm -

O_ l jih t " L. -

9r.= 1 eaww%uvs -

_ h r.rarmirmummmmn , S. =

Sij!LL"t rr m!,, . ., _

I e

@ l s s -

.l .,j,ffi,,j, .aif t

s. v w ,,

g ,

4

3 A Q ,r.s 7k '

l l

I I s -

Win .rl

~

MMI, "

7 ' H -

-(..}.; L.a - m a

g rt{]-

, sn m %.= q ~' i

s .
ma --

y I ,

d

/, ,k n

~- -m -

+ J .

t o . .

, u_

L_

,u n a .. ,

[ ,, -

== .- . , , .

i m:

rw . - .

i -

  • ll I . ;I',12 i

l - -

---fc

.,.gI, ..y. .1,c ; ee A ._.:. -

f .. ---

_w 1 I; ,l 4 x,.,

e

. gu .

. ~ - . . . . . .

.- ..$a1 nm 1 nm Da ent R,m i

Cross sectional view of the main building at hmolensk d-M.Ste 45/Mee efeem tubisse; a-enn.

7-tirst etese eendengte pum f-l*S/2fb t everbred trevelling etene; A-espereiwgdeem esperheeler;Js-neeln etreutet JJ-elettric deneer; 4-eddittenet reeler; r.p;ler presevre heefer; 8-desereter;4t remeief snetor of main circulating pump; Jo-detem erparator: J#-nelle- p-84/1eesattelled erehred itsvelliner erene;lline erene;d; #0-leetpum overhree trave #d- snec slaie; Jp-spedsler control haar beneath centrol RBMK 1990 peseter; Jf-teeldent eentainenent velges; JP-bubbler pend: J board reem; ##-house switchgeer letettene; #f-eebeest ventilatlen plant $3-plenusa ventitetless pient joenliene i

e I

1

  • l Smolensk Vertical Section, Showing Bubbler Pond.

[

\. .

Fig. 12 g

9 e

- - , ,. ,_.-.,,,--,m,_,.,_,-- ,, ,y ,,_.,.,_.g._g,, mm,_._7.._y,,.,,,m.,_,-..,,%, , , , . _

( '

,....--..g. .

?, -

1 sm r >

g

,s i

. S , '

! i o mi i 1 j E!- !f -

D~~ s a .5M =

$6 ,s sed *-

j -

' E!l i 3E d I

l~'

,, un r"'- %=ed, m

nu mg

_ r- .

. u z

,,. ' h I

! Imme mm i - -

d% ,

  1. },1 g '

5 s je l(o

j '
A

-- n - . ,

. m - .

/ /2 J AI i pass a ,

l d

.. e ., = . .

./ U ?m;!1 l

l /

,vnr2 swmw w.2/s7xx ar..wz ar.x.a u vs. ax,mu w II

/ / ///! I i / o 6 31 MM E R  ! 91 66 r g -

a

! M

' N g.

l l.,

li N -

6

. Building of as RBNKJ 2400 feester staties .

l

"$w*e*IY.D,'iLYdl:",#.".d!YE ",I'.'_'TJrE;Y.Yi/.Tr*EE4T.@.I.Ni.D#

1 fr%'"."J.at*31.nr.'7,L" ,T.T./.',.'TJ, WM.'r,'"4%, a't.".2"#4,/ir.'"f.,F.J l

Cu" '23:r! !! .M",41"W,'M"E. 'J;;2T!# 3:i'f.fi -"**""" '"" "-"

i i

4 l- e

{

, Fig. 13 RBMKP-2400 Reactor: Bubbler Pond is Included.

-t 4 i .

f -- - - - - - _ _ ___ _ __ ._ ._ . _ . . . - _ - _ _ _ _ _ _ _ _____, __ ___

. . . - . . . . .. .. . ._ , . . . . . . . .... .. .. ... j

/

(.

+e -

4 g=~ .

[L::;

~

s j

o ,

g- $3 u . . -

9 .I 2 - Production equipment g '[

/__L,?-f

' 3 - Upper pressure vehicle L ,' I .

4 - Grab drive

- 1 5 - Grab chains I

6 - Truss "U, 9 - Middle pressure vessel

. C / '. #/ ,

10- Shut-off device 77 _ i 12- Main television system 13- Removable shielding 3 14- Lower pressure vessel j g 17- Container Z3E IW 18- Gantry

19- carriage

~

L 1

bgbc .

e k .

,1. 1. cr.......ti.n .. .... 11n, M.. in..

. l . ... .. - - ~ ~ ^ - '. ~

~

-t

- ~

s/n '

.h.

11 -

bI N

2 # 1 - Housing

{

, 2 - Drive mechanisa 3 - G.ar Rack

-, 4 - Pinions 9, 5.- G.ar Rack wgA ,y 6 - Can L

,- 7 - Jaws

?

l l ~

.T.

4~

lc. .1,. ,, R. .. 11.. .R. . 1. . . .. < R. .. . .. .. .. 1 R.

..a 1o.

A u

i

~ ^ '

' ^ :: . ~ . . : L . . . . :. . ... . ~-

^ -

. T: : . .

~ .L .. . ~ ;. . : ~ ^ ^ . ... .

e .. v a . .

f s.

b peemenet pave

= = team,seenerensanes .

. enehas ans unen enmaaes

+

% ,, - emesses tenens seeenwesese

,

  • eneans esses es _t (seeket compressed M ,
" " "~

l A 5 Yh '

( g,a, N ___ . .

, pg o ,

,. , ,,,, 7 2 . C. ,.

. _e

%o l

% 11 A

9

} .

Q l  : .

M! K -

Ef

' 1 Siem 7 San -

!, .a nonee a nosenene s Ma*dne e spesine sleeve 4 screw to Presswe sleeve ii s support ring 11 easket q s Casing ,

l\

t' 1

Il

,, Fig. 16 Fuel Channel Top-End Closure.

i!

ti ,

t' 9 ot ME%e-335

&\

- _ _ _ - - _ _ - - _ _ _ - _ - _ . _ _ _ _ - - - - . .. -

Retrieved from "https://kanterella.com/w/index.php?title=ML20205N455&oldid=3326726"