3 edition of Assessment of RELAP5/MOD3.2 to the loss-of-residual-heat-removal event under shutdown condition found in the catalog.
Assessment of RELAP5/MOD3.2 to the loss-of-residual-heat-removal event under shutdown condition
Published
2000
by Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Supt. of Docs., U.S. G.P.O. [distributor] in Washington, DC
.
Written in English
Edition Notes
| Statement | prepared by K.W. Seul, Y.S. Bang, H.J. Kim. |
| Series | International agreement report -- NUREG/IA-0182. |
| Contributions | Bang, Y. S., Kim, H. J., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research., Hanʼguk Wŏnjaryŏk Anjŏn Kisurwŏn. |
| The Physical Object | |
|---|---|
| Format | Microform |
| Pagination | xiii, 51 p. |
| Number of Pages | 51 |
| ID Numbers | |
| Open Library | OL15573373M |
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Assessment of RELAP5/MOD to the loss-of-residual-heat-removal event under shutdown condition (SuDoc Y 3.N /) [K. Seul] on prosportsfandom.com *FREE* shipping on qualifying prosportsfandom.com: K.
Seul. Get this from a library. Assessment of RELAP5/MOD to the loss-of-residual-heat-removal event under shutdown condition. [K W Seul; Y S Bang; H J Kim; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.; Han'guk Wŏnjaryŏk Anjŏn Kisurwŏn.].
RELAP5/MOD post test analysis and accuracy quantification of SPES test SP-SB /. Add to Book Bag Remove from Book Bag. Saved in: Assessment of RELAP5/MOD3 with the LOFT L/L experiment simulating an anticipated transient with multiple failures / Assessment of RELAP5/MOD gamma with the LOFT L experiment simulating an.
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Seul. prosportsfandom.com Journal Article: Mitigation Measures Following a Loss-of-Residual-Heat-Removal Event During Shutdown. prosportsfandom.com Book: Loss of residual heat removal system simulation using CATHARE thermal hydraulic code.
The transient following a loss-of-residual-heat-removal event during shutdown was analyzed to determine the containment closure time (CCT) to prevent uncontrolled release of fission products and. This paper discusses the results obtained during an investigation of WWER Nuclear Power Plant (NPP) behavior at shutdown reactor during maintenance.
For the purpose of the analysis is selected a plant operating state with unsealed primary circuit by removing the MCP head. The reference nuclear power plant is Unit 6 at Kozloduy NPP (KNPP) prosportsfandom.com by: 1.
Correlation for countercurrent flow limitation in a PWR hot leg In the case of loss of residual heat removal systems under mid-loop operation during shutdown of a PWR plant, reflux cooling by. — — — — —, “The Use of Probabilistic Risk Assessment Methods in Nuclear Regulatory Activities,” August 16, RES Assessment Reports — — — — —, RPSB, “Containment/RCS Analysis of a Large-Break Loss-of-Coolant Accident in the AP Using RELAP5/MOD3,” August International Journal of Heat and Mass Transfer 44 () ± prosportsfandom.com Heat transfer ± a review of literature R.J.
Goldstein *, E.R. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
The safe storage of spent fuel assemblies in the spent fuel pools is very important. Thermal Engineering. in Power Systems. WITPRESS WIT Press publishes leading books in Science and Technology.
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