97101952 Neutronic model for modal multichannel analysis of out-of-phase instability in boiling water reactor cores Hashimoto. K. ct al. Anrt. Nncl. &erg??, 1997, 24, (2) 99-l I I. This paper presents a neutronic model for linear multichannel analysis of out-of-phase (regional) instability in a BWR
97/00423 US advanced liquid metal reactor (ALMR)
- Publisher
- Elsevier Science
- Year
- 1997
- Weight
- 199 KB
- Volume
- 38
- Category
- Article
- ISSN
- 0140-6701
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โฆ Synopsis
05 Nuclear fuels (economics, pohcy. supplies, forecasts) on a special parametrization nt the classical SPRT. The one-sided sequential test can reproduce the results of the Chien-Adams test when applied for mean values. 97/00416 Operating and test experience with EBR-II, the IFR prototype Sackett, .I. I.. I'ro~rc%v ;,I Nlr<~/eor Elzer~?', 1997. 31, (l/Z), 1 I I-12') The cxperimrntal breeder reactor number 2 (EBR-II) and its role in the operations and development of the industry is examined in this paper. The EBR-II ha\ operated for 30 years, the longest for any liquid metal cooled reactor (I.MR) power plant in the world and is arguably the most successful test reactor operation ever. Tests have been carried out on virtually every t&t reactor fuel tvpe. The reactor itself ha? been extensively studied. The mo\t dramatic saiety tests. conducted on 3 April, 19x6. showed that an I,MR with metallic fuel could safely accommodate loss of flow or loss of heat-\ink wlthout scram. EBR-II operated a\ the integral fast reactor (IFR) pr[,totype. demonrtrating important innovations in safety. plant design. fuel design and actinide recycle. The ahility to accommodate anticipated tran\lcnt\ without scram />~~.v.rn?lv resulted in significant simplification of the reactor plant. primarily through less reliance on emergency power and not having to require the secondary sodium or steam systems to he safety grade. The\e tcaturey have been quantified in a probabilistic risk a\csrmt'nt conducted for EBR-II. demonstrating considerable safet) advantages over other reactor concepts. Key to the superior safety and operating characteristics of thi\ reactor i+ the metallic U-Pu-Zr alloy fuel. A c~,mplrtr \ct of fuel performance and safety limit\ have been developed and included in formal satety.documents supporting comersinn of the core to IFK fuel. The last major demonstration planned was to assess the perhlrmance (of recycled actinides in the fuel and to contirm that pas\ibc \atet\ charactrri\tlc\ are maintained with recycled actinidc fuel in the core.
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