| LDR | 02463cam a2200409Ka 4500 | ||
| 001 | 102456341 | ||
| 003 | MiAaHDL | ||
| 005 | 20180827000000.0 | ||
| 006 | m d | ||
| 007 | cr bn ---auaua | ||
| 008 | 130724s1962 tnua b f000 0 eng d | ||
| 035 | ⊔ | ⊔ | ‡asdr-umn9973999744401701 |
| 035 | ⊔ | ⊔ | ‡a(OCoLC)853620703 |
| 040 | ⊔ | ⊔ | ‡aAZU ‡cAZU ‡dOCLCO ‡dOCLCA ‡dOCLCF |
| 086 | 0 | ⊔ | ‡aY 3.AT 7:22/GEAP-4130 |
| 100 | 1 | ⊔ | ‡aField, J. H. |
| 245 | 1 | 0 | ‡aExperimental studies of transient effects in fast reactor fuels. ‡nSeries I, ‡pUO₂ irradiations / ‡cby J. H. Field. |
| 260 | ⊔ | ⊔ | ‡aOak Ridge, Tenn. : ‡bU.S. Atomic Energy Commission, Division of Technical Information, ‡c1962. |
| 300 | ⊔ | ⊔ | ‡a74 pages : ‡billustrations (some folded) ; ‡c28 cm. |
| 336 | ⊔ | ⊔ | ‡atext ‡btxt ‡2rdacontent |
| 337 | ⊔ | ⊔ | ‡aunmediated ‡bn ‡2rdamedia |
| 338 | ⊔ | ⊔ | ‡avolume ‡bnc ‡2rdacarrier |
| 490 | 0 | ⊔ | ‡aGEAP (Series) ; ‡v4130 |
| 500 | ⊔ | ⊔ | ‡aWork performed at the General Electric Company, Atomic Power Equipment Department, San Jose, California. |
| 500 | ⊔ | ⊔ | ‡a"GEAP-4130; Metals, Ceramics, and Materials." |
| 500 | ⊔ | ⊔ | ‡a"November 15, 1962." |
| 504 | ⊔ | ⊔ | ‡aIncludes bibliographical references (page 74). |
| 520 | 3 | ⊔ | ‡aAn experimental program to evaluate the performance of FCR and EFCR fuel during transient operation is outlined, and the initial series of tests are described in some detail. Test results from five experiments in the TREAT reactor, using 1-in. OD SS-clad UO₂ fuel specimens, are compared with regard to fuel temperatures, mechanical integrity, and post-irradiation appearance. Incipient fuel pin failure limits for transients are identified with maximum fuel temperatures in the range of 7000 deg F. Multiple transient damage to the cladding is likely for transients above the melting point of the fuel. |
| 536 | ⊔ | ⊔ | ‡aPrepared by the General Electric Company for the U.S. Atomic Energy Commission under ‡bContract No. AT(04-3)-189, Project Agreement 10. |
| 538 | ⊔ | ⊔ | ‡aMode of access: Internet. |
| 583 | 1 | ⊔ | ‡awill digitize ‡c20130604 ‡zQueued for digitization June 4, 2013 ‡2pda ‡5miu |
| 650 | ⊔ | 7 | ‡aUranium oxides. ‡2fast ‡0(OCoLC)fst01162338 |
| 650 | ⊔ | 7 | ‡aNuclear fuels ‡xEffect of radiation on. ‡2fast ‡0(OCoLC)fst01040218 |
| 650 | ⊔ | 7 | ‡aFast reactors. ‡2fast ‡0(OCoLC)fst00921692 |
| 650 | ⊔ | 0 | ‡aFast reactors. |
| 650 | ⊔ | 0 | ‡aUranium oxides. |
| 650 | ⊔ | 0 | ‡aNuclear fuels ‡xEffect of radiation on. |
| 710 | 2 | ⊔ | ‡aGeneral Electric Company. ‡bAtomic Power Equipment Department. |
| 710 | 2 | ⊔ | ‡aU.S. Atomic Energy Commission. |
| 730 | 0 | ⊔ | ‡aTechnical Report Archive & Image Library (TRAIL) |
| CID | ⊔ | ⊔ | ‡a102456341 |
| DAT | 0 | ⊔ | ‡a20170408005514.0 ‡b20180827000000.0 |
| DAT | 1 | ⊔ | ‡a20180905090618.0 ‡b2024-05-13T18:33:16Z |
| CAT | ⊔ | ⊔ | ‡aSDR-UMN ‡dEX LIBRIS - ALMA ‡lprepare.pl-004-007 |
| FMT | ⊔ | ⊔ | ‡aBK |
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| 974 | ⊔ | ⊔ | ‡bUMN ‡cUMN ‡d20240513 ‡sgoogle ‡uumn.31951d038296919 ‡y1962 ‡rpd ‡qbib ‡tUS fed doc |