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IAEA-EBP-WWER-15 XA9950521 ...

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[I] Users Group for Soviet Designed Reactors (Report. WANO Symp.. Moscow, 1994).

[2] INTERNATIONAL ATOMIC ENERGY AGENCY. The Safety of WWER-440 Model 230 Nuclear Power Plants. STI/PUB/912. IAEA. Vienna (1992).

[3] Comparison of the Russian NPP safety concept contained in OBP 88 and the next lower levels norms/rules with the NUSS requirements. WWER-RD-069, 1994.

[4] INTERNATIONAL ATOMIC ENERGY AGENCY Evaluation of the Safety of Operating Nuclear Power Plants Built to Earlier Standards A Common Basis for Judgement, Safety Reports Series No. 12, IAEA, Vienna (1998).

[5] INTERNATIONAL ATOMIC ENERGY AGENCY, Code on the Safety of Nuclear Power Plants. 50-C-D (Rev. 1), IAEA. Vienna (1988).

[6] INTERNATIONAL ATOMIC ENERGY AGENCY, Ranking of Safety Issues for WWER-440 Model 230 Nuclear Power Plants, IAEA-TECDOC-640. Vienna (1992).

[7] INTERNATIONAL ATOMIC ENERGY AGENCY, Safety Issues and their Ranking for WWER-440 Model 213 NPPs. IAEA-EBP-WWER-03, Vienna (1996).

[8] INTERNATIONAL ATOMIC ENERGY AGENCY, RBMK NPPs Generic Safety Issues. IAEA-EBP-RBMK-04. Vienna (1995).

[9] INTERNATIONAL ATOMIC ENERGY AGENCY. Safety Issues and their Ranking for WWER 1000 Model 320 NPPs, IAEA-EBP-WWER-05 (1996).

[ 10] Review of Bubbler Condenser Structural Integrity Calculations, WWER-SC-142. 1995.

[II] Review of Bubbler Condenser Structural Integrity in Mochovce and Bohunice NPPs, (Report, Consultants Mtg, 1995), WWER-SC-159.

[12] Review of the Bubbler Condenser Structural Integrity in Dukovany NPP (Report, Expert Mission, May 1996), Dukovany, Czech Republic, WWER-SC-183.

[13] Third International Seminar on Horizontal Steam Generators, ISBN951-763-942-2, Lappeenranta, Finland (1994).

[14] Transient and Accident Analysis and Code Validation for WWER-440 Reactors (Report, Seminar, Helsinki, Finland, 1995), WWER-SC-168.

[ 15] INTERNATIONAL ATOMIC ENERGY AGENCY, Guidelines for Accident Analysis of WWER NPPs, IAEA-EBP-WWER-01, IAEA, Vienna (1995).

[16] INTERNATIONAL ATOMIC ENERGY AGENCY, Procedures for Analysis of Accidents in Shutdown Modes for WWER NPPs, IAEA-EBP-WWER-09, Vienna (1997).





[17] Transient and Accident Analysis of RBMK NPPs, RBMK-SC-052, 1997.

[18] Anticipated Transients without Scram for WWER-1000 Reactors, WWER-SC-186, 1996.

[19] Treatment of Primary to Secondary Leaks in WWER NPPs, Finland, WWER-SC-206, 1997.

[20] INTERNATIONAL ATOMIC ENERGY AGENCY. Guidelines on the PTS Analysis for WWER NPPs. IAEA-EBP-WWER-08, IAEA. Vienna (1997).

[21 ] INTERNATIONAL ATOMIC ENERGY AGENCY. Guidance for the Application of the Leak Before Break Concept, IAEA-TECDOC-774, Vienna (1994).

[22] INTERNATIONAL ATOMIC ENERGY AGENCY, Methodology for Qualification of In-Service Inspection Systems for WWER NPPs, IAEA-EBP-WWER-11. Vienna (1997).

[23] Evaluation guidelines for bubbler condenser metallic structure in WWER-440/213 NPPs containments (Report, Consultants Mtg, 1994). WWER-SC-095.

[24] Guidelines for WWER-440/213 containment evaluation (Report, Consultants Mtg. Dec.

1995). WWER-SC-170.

[25] INTERNATIONAL ATOMIC ENERGY AGENCY, Fire Hazard Analysis for WWER Nuclear Power Plants, IAEA-TECDOC-778, Vienna (1994).

[26] Workshop on Probabilistic Safety Assessment, Moscow, WWER-SC-053, 1992.

[27] Final Report of the Kola-1 PSA Review Workshop, 1992, WWER-RD-041.

[28] Review of a Top Level Risk Study for Kozloduy NPP Units 1-4 (Consultants Mtg, I992),WWER-SC-O39.

[29] Advances in reliability analysis and probabilistic safety assessment, Szentendre, Hungary, 1994, WWER-SC-116.

[30] IPERS -Paks NPP, 1993, WWER-RD-044.

[31 ] International Peer Review Service for Probabilistic Risk Assessment of the Bohunice VNPP, WWER-RD-043, 1993.

[32] PSA follow-up review workshop on the Level 1 probabilistic risk assessment of Kola 1 NPP, WWER-RD-066, 1993.

[33] INTERNATIONAL ATOMIC ENERGY AGENCY, Generic Initiating Events for PSA for WWER Reactors, IAEA-TECDOC-749, Vienna (1994).

[34] Leningrad NPP PSA Review, RBMK-SC-017, 1994.

[35] Report of IPERS Mission for Kozloduy Units 5&6, Bulgaria, WWER-SC-154, 1994.

[36] International peer review service for Level 1 PSA of Bohunice VI NPP, 1994, WWERRD-065.

[37] Level 1 PSA of the Paks NPP (Final Report of the Phase Review, 1994), WWERRD-070.

[38] Advances in Reliability Analysis and PSA, Szentendre, Hungary, 1994, WWER-SCTC-606.4.

[39] Insights from PSA Results on the Programmes for Safety Upgrading of WWER NPPs (Report, Consultants Mtg, Vienna, 1995), WWER-SC-152.

[40] Workshop notes, HSK 29/5 060-701-SWISRUS, Moscow, 1995.

[41] Report of the IPERS for the Bohunice V2 PSA Review Mission, 1995, WWER-SCReport of the IPERS Phase 1 for the Temelin PSA Review Missions, 1995, WWERSC-128.

[43] Report of IPERS Pre-Review Workshop for the Zaporozhe Unit 5, 1995, WWER-SCWorkshop on PSA Applications, Sofia, WWER-SC-198, 1996.

[45] Report on Harmonization of WWER PSA Model Assumptions & Data, Rez, Czech Republic, WWER-SC-195, 1996.

[46] Report of IPERS Phase 2 Review Mission for the Temelin NPP, Temelin, Czech Republic,WWER-SC-172, 1996.

[47] Workshop on Reliability Data for PSA, 1997, Bratislava, Slovakia, RER/9/046IAEA-RU-6964.

[48] PSA Peer Review (Kozloduy NPP Units 3 and 4), Sofia, Bulgaria, 1997, RER/9/046IAEA-RU-7443.

[49] Lecture Notes on Regional Workshop on External Events PSA, Moscow, 1998, WWER-SC-212, TC Project RER/9/046.

[50] Safety techniques and practices for evaluation and licensing of modifications in nuclear power plants built in accordance with early safety standards (Workshop, Obninsk, Russia, 1994), WWER-RD-075.

[51] Safety Evaluation of NPP Modifications and their Licensing, (Workshop, Santander, Spain, 1995), WWER-SC-132.

[52] INTERNATIONAL ATOMIC ENERGY AGENCY, Databases on Safety Issues for WWER and RBMK Reactors, IAEA-EBP-WWER-04, Vienna (1996).

[53] International Practices for RPV Integrity Assessment, 1996, Rez, Czech Republic, WWER-SC-193.

[54] Workshop on RBMK Fuel Channel Integrity, RBMK-SC-039, Kaunas, Lithuania, 1996.

[55] IAEA/SiP Senior Managers Workshop on International Promotion of Safety Culture for the NPPs with RBMK Reactors, 1996, Forsmark NPP, Sweden, RBMK-SC-046.

[56] Senior Managers Workshop on Promotion of Safety Culture for NPPs with RBMKs, 1997, Ignalina, RBMK-SC-051.

[57] Regulatory Assessment of the Safety Upgrading of Operational NPPs (IAEA Workshop, 1996, Leningrad, Russia), WWER-SC-191.

[58] Report of the Mtg on Conceptual Design Review of WWER-440/230 NPPs, WWERRD-019, 1991.

[59] Report on Safety Review Mission to Bohunice, WWER-RD-022, 1991.

[60] Kozloduy Safety Review Mission Report, WWER-RD-033, 1991.

[61 ] Novovoronezh Safety Review Mission Report, WWER-RD-034, 1991.

[62] Kola Safety Review Mission Report, WWER-RD-035, 1991.

[63] Safety Review Mission to Bohunice NPP, WWER-SC-038, 1992.

[64] Final Report of the World Bank and the IAEA Joint Mission to Armenia to review the Energy Sector Situation, Yerevan, Armenia, WWER-SC-041 (Revision 1) 1992.

[65] Kozloduy Safety Review Mission Follow-up, WWER-RD-049, 1993.

[66] Novovoronezh Safety Review Mission, WWER-RD-050, 1993.

[67] Kola Consultative Mission, WWER-RD-068, 1994.

[68] Compilation of Recommendations and Plant Programmes for the Safety Upgrading of WWER-440 Model 230 NPPs, WWER-RD-053, 1994.

[69] Bohunice V-1 Major Safety Upgrading; Piestany, WWER-RD-048, 1993.

[70] Major Improvements for WWER-440/230 NPPs (Report, Consultants Mtg,1993) WWER-RD-061.

[71 ] Database on WWER-440/230 Safety Issues and Plant Actions, WWER-SC-111, 1994.

[72] Safety Improvements of WWER-440/230 NPPs (Report, Consultants Mtg, 1994, Vienna), WWER-SC-107.

[73] Final Report of a Mission to Evaluate the Safety Conditions of the Restart of Armenia NPP, Erevan, 1993, TC Project ARM/9/002, WWER-RD-058.

[74] Report of a mission to evaluate the results of inspectors and the safety conditions of the restart of Armenia NPP, Erevan, Armenia, 1994, WWER-RD-079.

[75] Safety review mission to Armenia (under TC), WWER-RD-081, 1994.

[76] Final Report of a Technical Co-operation mission to evaluate the safety conditions of the restart of Armenia NPP (TC Projects ARM/9/003-11, 15, 17, ARM/9/008-06) Erevan, Armenia, WWER-SC-148, 1995.

[77] Report on Technical Visit to Novovoronezh Units 3 and 4, Russia, WWER-SC-161, 1995.

[78] Report of a Technical Visit organized by the IAEA to Bohunice NPP Units 1&2, Slovak Republic, WWER-SC-180, 1996.

[79] Report of a Technical Visit organized by the IAEA to Bohunice NPP Units 1&2, Slovak Republic, WWER-SC-164, 1996.

[80] Safety Improvements of WWER-440 Model 230 Nuclear Power Plants (Report, Consultants Mtg, 1998), WWER-SC-208, 1998.

[81] Confinement Improvement Options for NPPs with WWER-440/230 Plants, WWERSC-101, 1995.

[82] INTERNATIONAL ATOMIC ENERGY AGENCY, Reactor Pressure Vessel Embrittlement, IAEA-TECDOC-659, Vienna (1992).

[83] RPV Embrittlement and Annealing for WWER-440/230 (Report, Consultants Mtg, 1993), WWER-RD-072, April 1994 version.

[84] INTERNATIONAL ATOMIC ENERGY AGENCY, WWER-440/230 Reactor Pressure Vessel Integrity, IAEA-EBP-WWER-06, Vienna (1996).

[85] Round-Robin Exercise on WWER-440 RPV Weld Metal Irradiation Embrittlement, Annealing and Re-embrittlement; Terms of Reference, WWER-SC-192, 1996.

[86] Review of the safety condition of the restart of Armenia NPP Unit 2, Armenia, 1995 (Mission Report), TC ARM/9/003-11.

[87] Status of safety design improvements at Armenia NPP Unit 2, Armenia, 1996 (Mission Report), TC ARM/9/003-15.

[88] Status of safety design improvements at Armenia NPP Unit 2, Armenia, 1996 (Mission Report), TC ARM/9/003-17.

[89] Mission on reactor coolant system integrity of Kozloduy NPP, Kozloduy and Sofia, WWER-SC-109, 1994.

[90] Report of an expert mission to review the thermal-hydraulic stress and fracture mechanics analysis for Kozloduy NPP Units 1-4, Sofia, WWER-SC-126, 1995.

[91 ] Kozloduy Unit 1 RPV Integrity, Sofia, Bulgaria, WWER-SC-200, 1997.

[92] INTERNATIONAL ATOMIC ENERGY AGENCY, Applicability of the Leak Before Break Concept, IAEA-TECDOC-710, Vienna (1993).

[93] LBB Concept Application to the Jaslovske Bohunice NPP (Report, Consultants Mtg, 1993),WWER-RD-056, 1993.

[94] Expert Mission to review the LBB concept application to Kozloduy NPP 1-4, Sofia Bulgaria, WWER-SC-125, 1994.

[95] Review of LBB Concept Application to Kozloduy NPP Unit 1-4, Sofia, Bulgaria, WWER-SC-173, 1996.

[96] Containment and confinement performance, WWER-SC-085, Vienna, 1993.

[97] Review of the Methods Used for Leak Rate Measurements for WWER-440/230 Confinements and WWER-440/213 Containments (Report, Consultants Mtg 1995) WWER-SC-149.

[98] INTERNATIONAL ATOMIC ENERGY AGENCY, Design Basis and Design Features of WWER-440 Model 213 Nuclear Power Plants, IAEA-TECDOC-742, Vienna (1994).

[99] Safety enhancement and backfitting measures of WWER-440/V-213, WWER-SC-077, 1993.

[ 100] Backfittings & Safety Enhancement Measures in NPPs with WWER-440/213 Reactors, (Report, Consultants Mtg, 1994) WWER-SC-096.

[101] Safety Improvements Review (Mission to Mochovce NPP, 1993), WWER-SC-102 and WWER-RD-074.

[ 102] Safety Review Mission to Bohunice V2, WWER-RD-078, 1994.

[103] Ranking of safety issues for WWER-440/213 (Report, Consultants Mtg, 1994), WWER-SC-108.

[104] Analysis of WWER 1000 safety enhancement measures, WWER-SC-092, 1994.

[105] A Partial Assessment of the Safety of Stendal WWER-320/1000 NPP, GRS-112, IPSN-DES.

[106] Safety Evaluation of WWER-440/213 and WWER-1000/320 Reactors in Rovno NPP Units 1-2-3, Final Report (RWB), Risk Audit Report 7 (Vols. 1-2) (1994).

[ 107] Core Control and Protection Strategy of WWER-1000 (Report, Consultants Mtg, 1994) WWER-SC-071.

[108] Control Rod Insertion Reliability for WWER-1000 (Report, Consultants Mtg, 1995), WWER-SC-121.

[109] Review of the Safety Improvement Programme for South Ukraine NPP Units 1 and 2 to Identify the Safety Issues of 'Small Series' WWER-1000 NPPs, South Ukraine, Yuzhnoukrainsk, WWER-SC-182, 1996.

[110] Report of a Technical Visit to Novovoronezh NPP Unit 5, WWER-SC-199, 1997.

[Ill] Safety Issues and their Ranking for 'Small Series' WWER-1000 NPPs, WWER-SCReview of the Modernization Programme of the Kozloduy NPP Unit 5&6 (Report, Expert Mission, 1995), Kozloduy, Bulgaria, WWER-SC-143.

[113] Review of the Modernization Programme of Rovno NPP Unit 4 (Report, Expert Mission, 1995) Rovno, Ukraine, WWER-SC-151.

[114] Review of Modernization Programme of Khmelnitsky NPP Unit 2 (Report, Expert Mission, 1996), WWER-SC-178.

[115] Report of the Review of WWER-1000 Safety Issues Resolution at Temelin NPP, Temelin, Czech Republic, WWER-SC-171, 1996.

[116] Report on the Safety Review Mission to Zaporozhe NPP, WWER-RD-064, 1994.

[117] INTERNATIONAL ATOMIC ENERGY AGENCY, WWER-1000 Steam Generator Integrity, IAEA-EBP-WWER-07, Vienna (1997).

[118] IAEA Workshop on Safety Improvements of WWER-1000 Steam Generators, BINE, Beijing, IAEA-EBP-ASIA-02 (1997).

[119] Report of IAEA Technical Mtg on Physical Separation and Functional Isolation of Safety Systems for WWER-1000 Reactors, Vienna, WWER-SC-204, 1997.

[120] General Provisions for Ensuring Safety of NPPs, PNAE G-01-89, USSR (1989).

[121] Design and Safe Operation Rules for NPP Components and Piping, PNAE G-008-89, USSR (1989).

[122] Seismic Design Norms for NPPs, PNAE G-5-006-87, USSR (1987).Safety Analysis of Nuclear Power Plants during Low Power and Shutdown Conditions, IAEATECDOC-1042, Vienna (1998).

[123] Expert Mission to Evaluate the Russian Safety Standards used in the Design of the LiaoningNPP, 1996, EBP-ASIA-01 (1997).

[124] Primary to Secondary Cooling Circuit Leakages for WWER-1000 and WWER-440 NPPs (Report, CSM, Vienna, 1996), WWER-SC-179.

[125] INTERNATIONAL ATOMIC ENERGY AGENCY, Technical Basis for I&C Design Improvements in WWER 440/230 NPPs, IAEA-EBP-WWER-02, Vienna (1996).

[126] Safety Issues and Safety Improvement Measures connected with I&C WWER-440/213, (Report, Consultants Mtg) WWER-SC 106, 1994.

[127] IAEA contract report: Fire Hazard Study for WWER-440/230 NPP.

[128] INTERNATIONAL ATOMIC ENERGY AGENCY, Selected Safety Aspects of WWER-440 Model 213 Nuclear Power Plants, STI/PUB/1012, IAEA, Vienna (1996).

[129] Accident During Shutdown Conditions for WWER 1000 NPPs (Report, Consultants Mtg, 1995, Vienna), WWER-SC-153.

[130] INTERNATIONAL ATOMIC ENERGY AGENCY, Safety Analysis of Nuclear Power Plants during Low Power and Shutdown Conditions, IAEA-TECDOC-1042, Vienna (1998).

[131] INTERNATIONAL ATOMIC ENERGY AGENCY, Safety Assessment of Proposed Improvements to RBMK NPPs, IAEA-TECDOC-694, Vienna (1993).

[132] INTERNATIONAL ATOMIC ENERGY AGENCY, Safety Assessment of Design Solutions and Proposed Improvements to Smolensk NPP Unit 3 RBMK Nuclear Power Plant, IAEA-TECDOC-722, Vienna (1993).

[133] INTERNATIONAL ATOMIC ENERGY AGENCY, Safety Assessment of Proposed Modifications for Ignalina NPP, IAEA-EBP-RBMK-03, in English & Russian (1995).

[134] OS ART Mission Report to Ignalina NPP, 1995.

[135] Results of the IAEA Programme and EC Activities related to Safety of RBMK NPPs (Technical Committee Mtg, 1995), RBMK-SC-027.

[136] RBMK NPPs: Update of Safety Issues (Report of a Consultants Mtg, Vienna, 1997), RBMK-SC-053.

[137] Safety Analysis Report of Ignaiina NPP, 1996.

[138] Review of Ignalina NPP Safety Analysis Report, Risk Audit Report No. 55, 1997.

[139] Void Reactivity Feedback in RBMK NPPs, 1996, Moscow, RBMK-SC-042.

[ 140] Low Power Void Reactivity Feedback in RBMK NPPs, 1997, RBMK-SC-054.

[ 141 ] International Forum "One Decade After Chernobyl: Nuclear Safety Aspects", RBMKRD-006, 1996.

[142] SMIRT II Transactions Vol. M, Tokyo, Japan, 127-131.

[143] INTERNATIONAL ATOMIC ENERGY AGENCY, RBMK Shutdown Systems (English & Russian), IAEA-EBP-RBMK-01, Vienna (1995).

[ 144] RBMK Fuel Channel Integrity, 1997, RBMK-SC-050.

[ 145] Leak Before Break Concept Application to the RBMK NPPs, St. Petersburg, Russia, RBMK-SC-034, 1995.

[146] Regional Workshop on Environmentally-Assisted Cracking of NPP Austenitic Piping, Slavutych, Ukraine, RBMK-SC-060, 1998.

[147] Review of Guidance for LBB Concept Application to Ignalina NPP (Report, Workshop, 1998, Stockholm, Sweden), RBMK-SC-057.

[148] Report on the Technical Visit to the Leningrad NPP Unit 2, RBMK-SC-049, 1997.

[149] INTERNATIONAL ELECTROTECHNICAL COMMISSION, RBMK Nuclear Reactors Proposals for Instrumentation and Control Improvements (Technical Report), CEI-IEC 1510, Geneva (1996).

[150] Code validation for RBMK LOCA analysis (Report, Consultants Mtg, 1994, Japan), RBMK-SC-021.

[151] 3D Computer Codes for RBMK Core and System Analysis, Munich, RBMK-SC-048, 1996, [152] Core Damage States for NPP with RBMK Reactors (Report, CSM, 1996, Vienna), RBMK-SC-041.

[153] Updating of Understanding of the Causes of the Chernobyl Accident (Report, CSM, 1996, Russia), RBMK-SC-040.

[154] Chernobyl NPP Unit 2 Fire Accident, ASSET Mission Report, 1992.

[155] Report of the IAEA Mission to Chernobyl NPP, Ukraine, RBMK-RD-004, 1994.

[156] OS ART Follow-up to Ignalina NPP, 1997.

   

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IAEA-EBP-RBMK-01 RBMK Shutdown systems ( ) IAEA-EBP-RBMK-02 Multiple pressure tube rupture ( )

   

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IAEA-TECDOC-659 Reactor pressure vessel embrittlement IAEA-TECDOC-710 Applicability of the leak before break concept IAEA-TECDOC-722 Safety assessment of design solutions and proposed improvements

   

WWER-RD-004 Team's Analyses of Soviet Design WWERs DOE WWER-RD-022 Final Report of a Safety Review Mission organized by the IAEA to Bohunice Units 1&2 Nuclear Power Plant, CSFR Final Report of a Safety Review Mission organized by the IAEA WWER-RD-033 to Kozloduy Nuclear Power Plant Units I-IV, Kozloduy, Bulgaria

   

WWER-RD-035 Final report of a safety review mission organized by the IAEA to Poliarne Zori, USSR, Kola Units 1 and 2 WWER-RD-046 Review of the leak before break concept application to the Temelin WWER-1000 nuclear power plant WWER-RD-049 Kozloduy Safety Review Mission Follow up. Final Report of a Safety Review Mission Follow-up organized by the IAEA to Kozloduy NPP Units 1-4, Bulgaria

   

WWER-RD-071 CM on core control and protection Strategy of WWER-1000 Mochovce Safety Improvement Review: Report of consultants WWER-RD-074 meeting in Mochovce (Slovak Republic)

   

Report of a consultants meeting on containment and confinement WWER-SC-085 performance in NPPs with WWER 440/213 and 440/230 reactors

   

WWER-SC-106 Draft report of a consultants meeting on safety issues and safety improvement measures connected with instrumentation and control in NPPs with WWER-440/213 reactors

   

WWER-SC-121 Report on the consultants meeting on control rod insertion reliability for WWER 1000 nuclear power plants WWER-SC-125 Report of the experts' mission to review the LBB concept application to Kozloduy NPP 1-4, Sofia, Bulgaria

   

Report of a Consultants Meeting on the Review of Bubbler WWER-SC-142 Condenser Structural Integrity Calculations WWER-SC-143 Report of an Experts Mission to Review the Modernization Programme of the Kozloduy NPP Unit 5 & 6, Kozloduy, Bulgaria

   

WWER-SC-159 Report of an Experts Mission to Review the Bubbler Condenser Structural Integrity in Mochovce and Bohunice V-2 Nuclear Power Plants Report of an Experts Mission to Review the Safety Improvement WWER-SC-160 Programme in Dukovany Nuclear Power Plant, Czech Republic

   

Report of an Experts Mission to Review the Leak Before Break WWER-SC-173 Concept Application to Kozloduy Nuclear Power Plant Unitsl-4 WWER-1000 Steam Generator Integrity, Japan WWER-SC-176

   

Report of an Experts Mission to Review the Bubbler Condenser WWER-SC-183 Structural Integrity in Dukovany Nuclear Power Plant

   

Co-ordinated Research Programme: Round-Robin Exercise on WWER-SC-192 WWER-440 RPV Weld Metal Irradiation Embrittlement, Annealing and Re-embrittlement; Terms of Reference Workshop on International Practices for Reactor Pressure Vessel WWER-SC-193 Integrity Assessment, Rez, Czech Republic WWER-SC-197 Review the Safety Upgrading Programme of Paks NPP Units 1-4, Paks, Hungary

   

WWER-SC-205 Pressurized Thermal Shock Analysis Benchmark Exercise: Terms of Reference WWER-SC-206 Treatment of Primary to Secondary Leaks in WWER NPPs

   

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