Increasing the safety of atomic power stations with RBMK reactors
The authors review the operating, safety, and accident records of RBMK reactors in the Soviet Union, perform in-core kinetics assessments of cooling system, fuel element, and control rod behavior during accident scenarios, and make detailed technical recommendations for increasing the operating and...
Gespeichert in:
| Veröffentlicht in: | Sov. At. Energy (Engl. Transl.); (United States) 1987-04, Vol.62 (4), p.255-263 |
|---|---|
| Hauptverfasser: | , , , , , , , , , , |
| Format: | Artikel |
| Sprache: | eng |
| Schlagworte: | |
| Online-Zugang: | Volltext |
| Tags: |
Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
|
| container_end_page | 263 |
|---|---|
| container_issue | 4 |
| container_start_page | 255 |
| container_title | Sov. At. Energy (Engl. Transl.); (United States) |
| container_volume | 62 |
| creator | Adamov, E. O. Asmolov, V. G. Vasilevskii, V. P. Egorov, Yu. A. Kalugin, A. K. Nikitin, Yu. M. Nikolaev, V. A. Podlazov, L. N. Sirotkin, A. P. Stenbok, I. A. Cherkashov, Yu. M. |
| description | The authors review the operating, safety, and accident records of RBMK reactors in the Soviet Union, perform in-core kinetics assessments of cooling system, fuel element, and control rod behavior during accident scenarios, and make detailed technical recommendations for increasing the operating and safety margins of the plants. Methods for the amelioration of fission product release are also discussed. The Chernobyl accident is included. |
| doi_str_mv | 10.1007/BF01123364 |
| format | Article |
| fullrecord | <record><control><sourceid>crossref_osti_</sourceid><recordid>TN_cdi_crossref_primary_10_1007_BF01123364</recordid><sourceformat>XML</sourceformat><sourcesystem>PC</sourcesystem><sourcerecordid>10_1007_BF01123364</sourcerecordid><originalsourceid>FETCH-LOGICAL-c256t-d9c6cb2bff300ba914ec8c4498d037f274ba85f14eefb352d18fb0b350f20d593</originalsourceid><addsrcrecordid>eNpFUM1KAzEYDKJgqb34BMGjsPrlr8ke22JrsSKIgrcl-21iI3ZTkkDp27tSwbnMMMzMYQi5ZnDHAPT9fAmMcSGm8oyMmNKiMhzUORkBCFMpwT4uySTnLxggmBTMjMhs3WNyNof-k5ato9l6V440empL3AWk-3hwieZiS4h9podQtvR1_vxEhxaWmPIVufD2O7vJH4_J-_LhbfFYbV5W68VsUyFX01J1NU6x5a33AqC1NZMODUpZmw6E9lzL1hrlB9v5VijeMeNbGBR4Dp2qxZjcnHZjLqHJGIrDLca-d1gapbURWg6h21MIU8w5Od_sU9jZdGwYNL8nNf8niR_g8Vhx</addsrcrecordid><sourcetype>Open Access Repository</sourcetype><iscdi>true</iscdi><recordtype>article</recordtype></control><display><type>article</type><title>Increasing the safety of atomic power stations with RBMK reactors</title><source>SpringerLink Journals - AutoHoldings</source><creator>Adamov, E. O. ; Asmolov, V. G. ; Vasilevskii, V. P. ; Egorov, Yu. A. ; Kalugin, A. K. ; Nikitin, Yu. M. ; Nikolaev, V. A. ; Podlazov, L. N. ; Sirotkin, A. P. ; Stenbok, I. A. ; Cherkashov, Yu. M.</creator><creatorcontrib>Adamov, E. O. ; Asmolov, V. G. ; Vasilevskii, V. P. ; Egorov, Yu. A. ; Kalugin, A. K. ; Nikitin, Yu. M. ; Nikolaev, V. A. ; Podlazov, L. N. ; Sirotkin, A. P. ; Stenbok, I. A. ; Cherkashov, Yu. M.</creatorcontrib><description>The authors review the operating, safety, and accident records of RBMK reactors in the Soviet Union, perform in-core kinetics assessments of cooling system, fuel element, and control rod behavior during accident scenarios, and make detailed technical recommendations for increasing the operating and safety margins of the plants. Methods for the amelioration of fission product release are also discussed. The Chernobyl accident is included.</description><identifier>ISSN: 0038-531X</identifier><identifier>EISSN: 1573-8205</identifier><identifier>DOI: 10.1007/BF01123364</identifier><language>eng</language><publisher>United States</publisher><subject>210300 - Power Reactors, Nonbreeding, Graphite Moderated ; 220900 - Nuclear Reactor Technology- Reactor Safety ; ACCIDENTS ; ASIA ; CONTROL ELEMENTS ; COOLING SYSTEMS ; DOCUMENT TYPES ; EASTERN EUROPE ; EMERGENCY PLANS ; ENERGY SYSTEMS ; ENERGY TRANSFER ; EUROPE ; FISSION PRODUCT RELEASE ; FLUID MECHANICS ; FUEL CYCLE ; FUEL-CLADDING INTERACTIONS ; FUEL-COOLANT INTERACTIONS ; GENERAL STUDIES OF NUCLEAR REACTORS ; GRAPHITE MODERATED REACTORS ; HEAT TRANSFER ; HYDRAULICS ; INSPECTION ; KINETICS ; LWGR TYPE REACTORS ; MECHANICS ; NEUTRON ABSORBERS ; OPTIMIZATION ; POWER DISTRIBUTION ; PRIMARY COOLANT CIRCUITS ; RADIATION PROTECTION ; REACTIVITY ; REACTIVITY COEFFICIENTS ; REACTOR ACCIDENTS ; REACTOR COMPONENTS ; REACTOR COOLING SYSTEMS ; REACTOR CORES ; REACTOR KINETICS ; REACTOR SAFETY ; REACTORS ; REVIEWS ; SAFETY ; SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS ; SYSTEMS ANALYSIS ; TEMPERATURE EFFECTS ; USSR ; WATER COOLED REACTORS</subject><ispartof>Sov. At. Energy (Engl. Transl.); (United States), 1987-04, Vol.62 (4), p.255-263</ispartof><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c256t-d9c6cb2bff300ba914ec8c4498d037f274ba85f14eefb352d18fb0b350f20d593</citedby><cites>FETCH-LOGICAL-c256t-d9c6cb2bff300ba914ec8c4498d037f274ba85f14eefb352d18fb0b350f20d593</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><link.rule.ids>314,776,780,881,27901,27902</link.rule.ids><backlink>$$Uhttps://www.osti.gov/biblio/5778374$$D View this record in Osti.gov$$Hfree_for_read</backlink></links><search><creatorcontrib>Adamov, E. O.</creatorcontrib><creatorcontrib>Asmolov, V. G.</creatorcontrib><creatorcontrib>Vasilevskii, V. P.</creatorcontrib><creatorcontrib>Egorov, Yu. A.</creatorcontrib><creatorcontrib>Kalugin, A. K.</creatorcontrib><creatorcontrib>Nikitin, Yu. M.</creatorcontrib><creatorcontrib>Nikolaev, V. A.</creatorcontrib><creatorcontrib>Podlazov, L. N.</creatorcontrib><creatorcontrib>Sirotkin, A. P.</creatorcontrib><creatorcontrib>Stenbok, I. A.</creatorcontrib><creatorcontrib>Cherkashov, Yu. M.</creatorcontrib><title>Increasing the safety of atomic power stations with RBMK reactors</title><title>Sov. At. Energy (Engl. Transl.); (United States)</title><description>The authors review the operating, safety, and accident records of RBMK reactors in the Soviet Union, perform in-core kinetics assessments of cooling system, fuel element, and control rod behavior during accident scenarios, and make detailed technical recommendations for increasing the operating and safety margins of the plants. Methods for the amelioration of fission product release are also discussed. The Chernobyl accident is included.</description><subject>210300 - Power Reactors, Nonbreeding, Graphite Moderated</subject><subject>220900 - Nuclear Reactor Technology- Reactor Safety</subject><subject>ACCIDENTS</subject><subject>ASIA</subject><subject>CONTROL ELEMENTS</subject><subject>COOLING SYSTEMS</subject><subject>DOCUMENT TYPES</subject><subject>EASTERN EUROPE</subject><subject>EMERGENCY PLANS</subject><subject>ENERGY SYSTEMS</subject><subject>ENERGY TRANSFER</subject><subject>EUROPE</subject><subject>FISSION PRODUCT RELEASE</subject><subject>FLUID MECHANICS</subject><subject>FUEL CYCLE</subject><subject>FUEL-CLADDING INTERACTIONS</subject><subject>FUEL-COOLANT INTERACTIONS</subject><subject>GENERAL STUDIES OF NUCLEAR REACTORS</subject><subject>GRAPHITE MODERATED REACTORS</subject><subject>HEAT TRANSFER</subject><subject>HYDRAULICS</subject><subject>INSPECTION</subject><subject>KINETICS</subject><subject>LWGR TYPE REACTORS</subject><subject>MECHANICS</subject><subject>NEUTRON ABSORBERS</subject><subject>OPTIMIZATION</subject><subject>POWER DISTRIBUTION</subject><subject>PRIMARY COOLANT CIRCUITS</subject><subject>RADIATION PROTECTION</subject><subject>REACTIVITY</subject><subject>REACTIVITY COEFFICIENTS</subject><subject>REACTOR ACCIDENTS</subject><subject>REACTOR COMPONENTS</subject><subject>REACTOR COOLING SYSTEMS</subject><subject>REACTOR CORES</subject><subject>REACTOR KINETICS</subject><subject>REACTOR SAFETY</subject><subject>REACTORS</subject><subject>REVIEWS</subject><subject>SAFETY</subject><subject>SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS</subject><subject>SYSTEMS ANALYSIS</subject><subject>TEMPERATURE EFFECTS</subject><subject>USSR</subject><subject>WATER COOLED REACTORS</subject><issn>0038-531X</issn><issn>1573-8205</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>1987</creationdate><recordtype>article</recordtype><recordid>eNpFUM1KAzEYDKJgqb34BMGjsPrlr8ke22JrsSKIgrcl-21iI3ZTkkDp27tSwbnMMMzMYQi5ZnDHAPT9fAmMcSGm8oyMmNKiMhzUORkBCFMpwT4uySTnLxggmBTMjMhs3WNyNof-k5ato9l6V440empL3AWk-3hwieZiS4h9podQtvR1_vxEhxaWmPIVufD2O7vJH4_J-_LhbfFYbV5W68VsUyFX01J1NU6x5a33AqC1NZMODUpZmw6E9lzL1hrlB9v5VijeMeNbGBR4Dp2qxZjcnHZjLqHJGIrDLca-d1gapbURWg6h21MIU8w5Od_sU9jZdGwYNL8nNf8niR_g8Vhx</recordid><startdate>19870401</startdate><enddate>19870401</enddate><creator>Adamov, E. O.</creator><creator>Asmolov, V. G.</creator><creator>Vasilevskii, V. P.</creator><creator>Egorov, Yu. A.</creator><creator>Kalugin, A. K.</creator><creator>Nikitin, Yu. M.</creator><creator>Nikolaev, V. A.</creator><creator>Podlazov, L. N.</creator><creator>Sirotkin, A. P.</creator><creator>Stenbok, I. A.</creator><creator>Cherkashov, Yu. M.</creator><scope>AAYXX</scope><scope>CITATION</scope><scope>OTOTI</scope></search><sort><creationdate>19870401</creationdate><title>Increasing the safety of atomic power stations with RBMK reactors</title><author>Adamov, E. O. ; Asmolov, V. G. ; Vasilevskii, V. P. ; Egorov, Yu. A. ; Kalugin, A. K. ; Nikitin, Yu. M. ; Nikolaev, V. A. ; Podlazov, L. N. ; Sirotkin, A. P. ; Stenbok, I. A. ; Cherkashov, Yu. M.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c256t-d9c6cb2bff300ba914ec8c4498d037f274ba85f14eefb352d18fb0b350f20d593</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>1987</creationdate><topic>210300 - Power Reactors, Nonbreeding, Graphite Moderated</topic><topic>220900 - Nuclear Reactor Technology- Reactor Safety</topic><topic>ACCIDENTS</topic><topic>ASIA</topic><topic>CONTROL ELEMENTS</topic><topic>COOLING SYSTEMS</topic><topic>DOCUMENT TYPES</topic><topic>EASTERN EUROPE</topic><topic>EMERGENCY PLANS</topic><topic>ENERGY SYSTEMS</topic><topic>ENERGY TRANSFER</topic><topic>EUROPE</topic><topic>FISSION PRODUCT RELEASE</topic><topic>FLUID MECHANICS</topic><topic>FUEL CYCLE</topic><topic>FUEL-CLADDING INTERACTIONS</topic><topic>FUEL-COOLANT INTERACTIONS</topic><topic>GENERAL STUDIES OF NUCLEAR REACTORS</topic><topic>GRAPHITE MODERATED REACTORS</topic><topic>HEAT TRANSFER</topic><topic>HYDRAULICS</topic><topic>INSPECTION</topic><topic>KINETICS</topic><topic>LWGR TYPE REACTORS</topic><topic>MECHANICS</topic><topic>NEUTRON ABSORBERS</topic><topic>OPTIMIZATION</topic><topic>POWER DISTRIBUTION</topic><topic>PRIMARY COOLANT CIRCUITS</topic><topic>RADIATION PROTECTION</topic><topic>REACTIVITY</topic><topic>REACTIVITY COEFFICIENTS</topic><topic>REACTOR ACCIDENTS</topic><topic>REACTOR COMPONENTS</topic><topic>REACTOR COOLING SYSTEMS</topic><topic>REACTOR CORES</topic><topic>REACTOR KINETICS</topic><topic>REACTOR SAFETY</topic><topic>REACTORS</topic><topic>REVIEWS</topic><topic>SAFETY</topic><topic>SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS</topic><topic>SYSTEMS ANALYSIS</topic><topic>TEMPERATURE EFFECTS</topic><topic>USSR</topic><topic>WATER COOLED REACTORS</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Adamov, E. O.</creatorcontrib><creatorcontrib>Asmolov, V. G.</creatorcontrib><creatorcontrib>Vasilevskii, V. P.</creatorcontrib><creatorcontrib>Egorov, Yu. A.</creatorcontrib><creatorcontrib>Kalugin, A. K.</creatorcontrib><creatorcontrib>Nikitin, Yu. M.</creatorcontrib><creatorcontrib>Nikolaev, V. A.</creatorcontrib><creatorcontrib>Podlazov, L. N.</creatorcontrib><creatorcontrib>Sirotkin, A. P.</creatorcontrib><creatorcontrib>Stenbok, I. A.</creatorcontrib><creatorcontrib>Cherkashov, Yu. M.</creatorcontrib><collection>CrossRef</collection><collection>OSTI.GOV</collection><jtitle>Sov. At. Energy (Engl. Transl.); (United States)</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Adamov, E. O.</au><au>Asmolov, V. G.</au><au>Vasilevskii, V. P.</au><au>Egorov, Yu. A.</au><au>Kalugin, A. K.</au><au>Nikitin, Yu. M.</au><au>Nikolaev, V. A.</au><au>Podlazov, L. N.</au><au>Sirotkin, A. P.</au><au>Stenbok, I. A.</au><au>Cherkashov, Yu. M.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Increasing the safety of atomic power stations with RBMK reactors</atitle><jtitle>Sov. At. Energy (Engl. Transl.); (United States)</jtitle><date>1987-04-01</date><risdate>1987</risdate><volume>62</volume><issue>4</issue><spage>255</spage><epage>263</epage><pages>255-263</pages><issn>0038-531X</issn><eissn>1573-8205</eissn><abstract>The authors review the operating, safety, and accident records of RBMK reactors in the Soviet Union, perform in-core kinetics assessments of cooling system, fuel element, and control rod behavior during accident scenarios, and make detailed technical recommendations for increasing the operating and safety margins of the plants. Methods for the amelioration of fission product release are also discussed. The Chernobyl accident is included.</abstract><cop>United States</cop><doi>10.1007/BF01123364</doi><tpages>9</tpages></addata></record> |
| fulltext | fulltext |
| identifier | ISSN: 0038-531X |
| ispartof | Sov. At. Energy (Engl. Transl.); (United States), 1987-04, Vol.62 (4), p.255-263 |
| issn | 0038-531X 1573-8205 |
| language | eng |
| recordid | cdi_crossref_primary_10_1007_BF01123364 |
| source | SpringerLink Journals - AutoHoldings |
| subjects | 210300 - Power Reactors, Nonbreeding, Graphite Moderated 220900 - Nuclear Reactor Technology- Reactor Safety ACCIDENTS ASIA CONTROL ELEMENTS COOLING SYSTEMS DOCUMENT TYPES EASTERN EUROPE EMERGENCY PLANS ENERGY SYSTEMS ENERGY TRANSFER EUROPE FISSION PRODUCT RELEASE FLUID MECHANICS FUEL CYCLE FUEL-CLADDING INTERACTIONS FUEL-COOLANT INTERACTIONS GENERAL STUDIES OF NUCLEAR REACTORS GRAPHITE MODERATED REACTORS HEAT TRANSFER HYDRAULICS INSPECTION KINETICS LWGR TYPE REACTORS MECHANICS NEUTRON ABSORBERS OPTIMIZATION POWER DISTRIBUTION PRIMARY COOLANT CIRCUITS RADIATION PROTECTION REACTIVITY REACTIVITY COEFFICIENTS REACTOR ACCIDENTS REACTOR COMPONENTS REACTOR COOLING SYSTEMS REACTOR CORES REACTOR KINETICS REACTOR SAFETY REACTORS REVIEWS SAFETY SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS SYSTEMS ANALYSIS TEMPERATURE EFFECTS USSR WATER COOLED REACTORS |
| title | Increasing the safety of atomic power stations with RBMK reactors |
| url | https://sfx.bib-bvb.de/sfx_tum?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&ctx_tim=2025-02-07T12%3A33%3A06IST&url_ver=Z39.88-2004&url_ctx_fmt=infofi/fmt:kev:mtx:ctx&rfr_id=info:sid/primo.exlibrisgroup.com:primo3-Article-crossref_osti_&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.atitle=Increasing%20the%20safety%20of%20atomic%20power%20stations%20with%20RBMK%20reactors&rft.jtitle=Sov.%20At.%20Energy%20(Engl.%20Transl.);%20(United%20States)&rft.au=Adamov,%20E.%20O.&rft.date=1987-04-01&rft.volume=62&rft.issue=4&rft.spage=255&rft.epage=263&rft.pages=255-263&rft.issn=0038-531X&rft.eissn=1573-8205&rft_id=info:doi/10.1007/BF01123364&rft_dat=%3Ccrossref_osti_%3E10_1007_BF01123364%3C/crossref_osti_%3E%3Curl%3E%3C/url%3E&disable_directlink=true&sfx.directlink=off&sfx.report_link=0&rft_id=info:oai/&rft_id=info:pmid/&rfr_iscdi=true |