IRRADIATION DOSE EVALUATION DURING INTEGRAL REACTOR DECOMMISSIONING

Because the activity and mass of radioactive equipment of the integral reactors considered are substantially lower than those ones of conventional NPP reactors, this influences irradiation doses.

According to calculations personnel irradiation dose during VPBER-600 and AST-500 unit decommissioning is 2.5-3.5 man. Sv taking account of plant-level systems).

The radiological effect on the inhabitants during decommissioning was evaluated proceeding from the amount of radioactive product releases which can enter the atmosphere. The result obtained was that during AST-500 equipment and reactor vessel disassembly the reactivity release to the atmosphere including cleaning in wet scrubbers and aerosol filters gives the value ~3 mCi for Co 60, that is -20% of the specified limit.

6. COMPARISON OF DECOMMISSIONING CONDITIONS FOR INTEGRAL AND

VVER-TYPE REACTORS

The advantages of integral reactor decommissioning emerge when comparing decommissioning conditions for VPBER-600 and VVER-440 "Lovisa" (Fig.9).

The concept of "immediate" dismounting in 2 years following termination of preparatory work is suggested both for "Lovisa” and VPBER-600 reactors. The main problem of NPP "Lovisa" decommissioning is the handling of the hot reactor vessel which must be broken up in hot chambers by remotely controlled equipment and be removed in large thick-walled casks to stores or the reactor vessel and equipment must be removed and disposed off as a whole. One should note that special manipulators and other expensive facilities are not required for breaking up the VPBER-600 reactor vessel.

Comparison results show that in spite of higher power a more prolonged operation period and shorter hold-up time following shutdown, safety characteristics (activity value, radwaste amount, irradiation doses) during VPBER-600 reactor decommissioning are tens and hundreds times smaller than those for VVER-440 reactor.

7. CONCLUSION

So, the structural features of AST and VPBER reactors (including the integral layout of their main primary equipment and location of a leaktighr reactor in an additional guard vessel) ultimately simplify the technologically difficult, radiologically dangerous and expensive decommissioning of PWR (VVER)-type NPP reduce the amount of radwaste and the costs and make integral reactor decommissioning safe for both personnel and inhabitants.

LIST OF PARTICIPANTS

Achkasov, A. N.

Research and Development Institute of Power Engineering (RDIPE)

Malaya Krasnoselskaya st. h. 2/8 Moscow

Russian Federation

Adamovich, L. A.

Research and Development Institute of Power Engineering (RDIPE)

Malaya Krasnoselskaya st. h. 2/8 Moscow

Russian Federation

Al-Mugrabi, M. A. (Scientific Secretary)

IAEA, Division of Nuclear Power

Wagramerstrasse -5

P. O. Box 100

A-1400 Vienna, Austria

Altshuller, M.

All-Union Research Institute for Nuclear Power

Plant Operations

Ferganskaya 25

109507 Moscow

Russian Federation

Antariksawan, A. R.

Nattional Atomic Energy Agency (BATAN) Kawasan Puspiptek Serpong Tangerang 15310 Indonesia

Baranaev, Yu. D.

Institute of Physics and Power Engineering (IPPE) Bondarenko Sq. 1 249020 Obninsk Russian Federation

Boado, H. M.

INVAP S. E.

Moreno 2089

San Carlos de Bariloche

(CP 8400), Argentina

Buhtoyarov, A. V.

EDO “Gidropress” Ordzhonikidze st. 21 142103 Moscow District Podolsk

Russian Federation

Cinotti, L.

Advanced Reactors Project Engineer

ANSALDO

Nuclear Division

Corso Perrone 25

16161 Genova, Italy

Dolgov, V. N.

St. Petersburgh Marine Engineering Bureau “Malachite” Frunze Str. 18 196135 St. Petersburg Russian Federation

Dolgov, V. V.

Institute of Physics and Power Engineering (IPPE) Bondarenko Sq. 1 249020 Obninsk Russian Federation

Dzhusow, Y.

Institute of Physics and Power Engineering (IPPE) Bondarenko Sq. 1 249020 Obninsk Russian Federation

Erastov, A.

MINATOM

Staromonetny pereulok 26 109180 Moscow Russian Federation

Gibson, I.

3, Hardy Close Martinstown, Dorchester DT2 9JS Dorset United Kingdom

Grachev, N.

Institute of Physics and Power Engineering (IPPE) Bondarenko Sq. 1 249020 Obninsk Russian Federation

Grechko, G. I.

Research and Development Institute of Power Engineering (RDIPE)

Malaya Krasnoselskaya st. h. 2/8 Moscow

Russian Federation

Grigoriev, 0.

Institute of Physics and Power Engineering (IPPE) Bondarenko Sq. 1 249020 Obninsk Russian Federation

Hey, H. M.

CNEA

Kalyakin, S.

Av. Libertador 8250 1429 Buenos Aires Argentina

Institute of Physics and Power Engineering (IPPE) Bondarenko Sq. 1 249020 Obninsk Russian Federation

Kim, J. I.

Korea Atomic Energy Research Institute (KAERI) P. O. Box 105, Yusung Taejon 305-606 Republic of Korea

Kozmenkov, Y. K.

Institute of Physics and Power Engineering (IPPE) Bondarenko Sq. 1 249020 Obninsk Russian Federation

Kusmartsev, E.

OKB Mechanical Engineering Bumakovsky proezd 15 603074 Nizhny Novgorod Russian Federation

Kuul, V.

OKB Mechanical Engineering Bumakovsky proezd 15 603074 Nizhny Novgorod Russian Federation

Kuzachenkov, A. B.

OKB Mechanical Engineering Bumakovsky proezd 15 603074 Nizhny Novgorod Russian Federation

Lapin, D. B.

Research and Development Institute of Power Engineering (RDIPE)

Malaya Krasnoselskaya st. h. 2/8 Moscow, Russian Federation

Leger, A.

TECHNICATOME

BP 17, 91192 Gif-sur-Yvette

France

Lee, D.

Korea Atomic Energy Research Institute (KAERI) P. O. Box 105, Yusung Taejon 305-606 Republic of Korea

Leonchyk, M.

Institute of Physics and Power Engineering (IPPE) Bondarenko Sq. 1 249020 Obninsk Russian Federation

Li, M.

Nuclear Power Institute of China P. O. Box 436-500 Chengdu, Sichuan Province China

Lusanova, L. M.

Russian Research Centre “Kurchatov Institute” Kurchatov Square 123182 Moscow Russian Federation

Ma, C.

Institute of Nuclear Energy Technology Tsinghua University 100084 Beijing China

Nikiporets, Yu. G.

Russian Research Centre “Kurchatov Institute” Kurchatov Square 123182 Moscow Russian Federation

Nikolaeva, A. N.

St. Petersburgh Marine Engineering Bureau “Malachite” Frunze Str. 18 196135 St. Petersburg Russian Federation

Orekhov, Y. I.

Institute of Physics and Power Engineering (IPPE) Bondarenko Sq. 1 249020 Obninsk Russian Federation

Pepa, V. N.

Research and Development Institute of Power Engineering (RDIPE)

Malaya Krasnoselskaya st. h. 2/8 Moscow

Russian Federation

Pokrovskaya, I. N.

Research and Development Institute of Power Engineering (RDIPE)

Malaya Krasnoselskaya st. h. 2/8 Moscow

Russian Federation

Rulev, V.

 

OKB Mechanical Engineering Bumakovsky proezd 15 603074 Nizhny Novgorod Russian Federation

Institute of Physics and Power Engineering (IPPE) Bondarenko Sq. 1 249020 Obninsk Russian Federation

Institute of Physics and Power Engineering (IPPE) Bondarenko Sq. 1 249020 Obninsk Russian Federation

Institute of Physics and Power Engineering (IPPE) Bondarenko Sq. 1 249020 Obninsk Russian Federation

Institute of Physics and Power Engineering (IPPE) Bondarenko Sq. 1 249020 Obninsk Russian Federation

Research Technology Institute 188537 Sosnovy Bor Leningrad Region Russian Federation

“ Baltsudoproject ”

Griboedova canal 90 St. Petersburg Russian Federation

Japan Atomic Energy Research Institute — JAERI

Tokai-mura, Naka-gun, Ibaraki-ken 319-11 Japan

Russian Federation Ministry for Atomic Energy Staromonetny pereulok 26 109180 Moscow Russian Federation

 

Sergeev, Yu. A.

 

Shumsky, R.

 

Shvedenko, I.

 

Skorikov, D.

 

Vitin, S.

 

Vorobev, V.

 

Yamaji, A.

 

Zverev, K.

 

[1] Dimensions were taken from available literature. Heights and weights of vessels were determined approximately after subtracting the ones of covers.

[2] Dimensions and weights have been determined from Г21. 13].[4] by approximation after subtracting covers.

From the comparison of pressure vessels of PVRs. BVRs and those of integral reactors it follows, that diameters and lengths of last ones are comparable with those of BVRs. Due to the higher operating pressure which is equal to operating pressure of PVRs. walls of integral reactor vessels are more thick (in the range of 250 — 300 mm) and their weights exceed the weight of the to date heaviest RPV of ATUCHA 2 (975 t).