Assessment of RELAP5/MOD3.1 using LSTF ten-percent main steam-line-break test run SB-SL-01 / prepared by J.G. Oh [and seven others].
Record details
- Physical Description: 1 online resource (viii, 111 pages) : illustrations.
- Publisher: Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, September 1998.
Content descriptions
| General Note: | "Korea Power Engineering Company." "Korea Institute of Nuclear Safety." "Japan Atomic Energy Research Institute." "September 1998." "Prepared as part of the Agreement on Research Participation and Technical Exchange under the International Thermal-Hydraulic Code Assessment and Maintenance Program (CAMP)." "G. Rhee, NRC project manager"--Bibliographic data sheet. |
| Bibliography, etc. Note: | Includes bibliographical references (page 29). |
| Funding Information Note: | Sponsored by the Division of Systems Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission D6227 |
| Source of Description Note: | Description based on online resource; title from PDF title page (viewed on July 28, 2017). |
Search for related items by subject
| Subject: | Pressurized water reactors > Loss of coolant > Computer programs > Testing. |
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| LDR | 02415nam a2200433Ii 4500 | ||
|---|---|---|---|
| 001 | ocn999350634 | ||
| 003 | OCoLC | ||
| 005 | 20170803132816.0 | ||
| 006 | m o d f | ||
| 007 | cr ||||||||||| | ||
| 008 | 170803e199809 dcua gobt f000 0 eng d | ||
| 035 | . | ‡a(OCoLC)ocn999350634 | |
| 040 | . | ‡aGPO ‡beng ‡erda ‡epn ‡cGPO ‡dMvI ‡dMvI | |
| 074 | . | ‡a1051-H-41 (online) | |
| 086 | 0 | . | ‡aY 3.N 88:53/0148 |
| 100 | 1 | . | ‡aOh, J. G., ‡eauthor. |
| 245 | 1 | 0. | ‡aAssessment of RELAP5/MOD3.1 using LSTF ten-percent main steam-line-break test run SB-SL-01 / ‡cprepared by J.G. Oh [and seven others]. |
| 264 | 1. | ‡aWashington, DC : ‡bOffice of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, ‡cSeptember 1998. | |
| 300 | . | ‡a1 online resource (viii, 111 pages) : ‡billustrations. | |
| 336 | . | ‡atext ‡btxt ‡2rdacontent | |
| 337 | . | ‡acomputer ‡bc ‡2rdamedia | |
| 338 | . | ‡aonline resource ‡bcr ‡2rdacarrier | |
| 490 | 1 | . | ‡aInternational agreement report ; ‡vNUREG/IA-0148 |
| 588 | . | ‡aDescription based on online resource; title from PDF title page (viewed on July 28, 2017). | |
| 500 | . | ‡a"Korea Power Engineering Company." | |
| 500 | . | ‡a"Korea Institute of Nuclear Safety." | |
| 500 | . | ‡a"Japan Atomic Energy Research Institute." | |
| 500 | . | ‡a"September 1998." | |
| 500 | . | ‡a"Prepared as part of the Agreement on Research Participation and Technical Exchange under the International Thermal-Hydraulic Code Assessment and Maintenance Program (CAMP)." | |
| 500 | . | ‡a"G. Rhee, NRC project manager"--Bibliographic data sheet. | |
| 504 | . | ‡aIncludes bibliographical references (page 29). | |
| 536 | . | ‡aSponsored by the Division of Systems Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission ‡cD6227 | |
| 650 | 0. | ‡aPressurized water reactors ‡xLoss of coolant ‡0(DLC)sh 85106564 ‡xComputer programs ‡0(DLC)sh 99005296 ‡xTesting. ‡0(DLC)sh 99005648 | |
| 710 | 2 | . | ‡aU.S. Nuclear Regulatory Commission. ‡bOffice of Nuclear Regulatory Research. ‡bDivision of Systems Technology, ‡0(DLC)no 95015370 ‡esponsoring body. |
| 776 | 0 | 8. | ‡iMicrofiche version: ‡aOh, J. G. ‡tAssessment of RELAP5/MOD3.1 using LSTF ten-percent main steam-line-break test run SB-SL-01 ‡w(OCoLC)42738543 |
| 830 | 0. | ‡aInternational agreement report ; ‡0(DLC)n 86729091 ‡vNUREG/IA-0148. | |
| 856 | 4 | 0. | ‡uhttps://purl.fdlp.gov/GPO/gpo83169 ‡9STLIB-IND |
| 949 | . | ‡hONLINE | |
| 901 | . | ‡aocn999350634 ‡bOCoLC ‡c21108627 ‡tbiblio ‡sGPO - Government Documents | |
