Computation of initial stage of RBMK reactor fuel channel vessel rupture

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Objective of this work is estimation of temperature and time characteristics for rupture of the zirconium pipe which is the RBMK reactor fuel channel (FC) vessel under emergencies. As an emergency the zirconium pipe temperature rise process is considered which results in loss of pipe material strength properties and pipe rupture under the action of internal pressure P=80MPa. The work was carried out under Task Order 007 of University of California - VNIIEF Subcontract No. 0002P0004-95. The problem formulation is stated in Protocol (Task 3, Appendix 3) of the Russian-American Workshop which was held in December, 1994 in Los Alamos. ... continued below

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29 p.

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Pevnitsky, A.V.; Solovyev, V.P. & Abakumov, A.I. December 31, 1995.

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Description

Objective of this work is estimation of temperature and time characteristics for rupture of the zirconium pipe which is the RBMK reactor fuel channel (FC) vessel under emergencies. As an emergency the zirconium pipe temperature rise process is considered which results in loss of pipe material strength properties and pipe rupture under the action of internal pressure P=80MPa. The work was carried out under Task Order 007 of University of California - VNIIEF Subcontract No. 0002P0004-95. The problem formulation is stated in Protocol (Task 3, Appendix 3) of the Russian-American Workshop which was held in December, 1994 in Los Alamos. Physical-mechanical and geometry characteristics of structure elements (FC vessel with graphite ring and graphite slug) are presented by NIKIET. The temperature mode of the structure is taken in conformity with the NIKIET data obtained with the RELAP5/MOD3 code. Numerical simulation of structure element behavior in an emergency is performed using the DRAKON program comlex oriented to solving strength problems for complex spatial structures at intense dynamic loading. The {open_quotes}DRAKON{close_quotes} program complex is described and compared with similar western codes in its capabilities.

Physical Description

29 p.

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INIS; OSTI as DE96009519

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  • Other Information: PBD: 1995

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  • Other: DE96009519
  • Report No.: LA-SUB--96-51-Pt.1
  • Grant Number: W-7405-ENG-36
  • DOI: 10.2172/219465 | External Link
  • Office of Scientific & Technical Information Report Number: 219465
  • Archival Resource Key: ark:/67531/metadc669410

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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  • December 31, 1995

Added to The UNT Digital Library

  • June 29, 2015, 9:42 p.m.

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  • Feb. 25, 2016, 2:10 p.m.

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Pevnitsky, A.V.; Solovyev, V.P. & Abakumov, A.I. Computation of initial stage of RBMK reactor fuel channel vessel rupture, report, December 31, 1995; New Mexico. (digital.library.unt.edu/ark:/67531/metadc669410/: accessed June 21, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.