Reference Citation Analysis: Find an Article, Find a Category, Find a Journal, Find a Scholar

For:	Straalsund JL, Fish RL, Johnson GD. Correlation of Transient-Test Data with Conventional Mechanical Properties Data. NUCL TECHNOL 2017. [DOI: 10.13182/nt75-a24390] [Citation(s) in RCA: 17] [Impact Index Per Article: 2.4] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]

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Cited by Other Article(s)

Sanyal G. Axial crack resistance of cladding tubes for fast reactors. ANN NUCL ENERGY 2017. [DOI: 10.1016/j.anucene.2017.07.003] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]

Duncan DR. Effect of Prior Irradiation Creep on the Subsequent Burst Strength of 20% Cold-Worked Type 316 Stainless-Steel Cladding. NUCL TECHNOL 2017. [DOI: 10.13182/nt78-a32078] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]

Cannon NS, Wire GL. Controlled Biaxial Strain-Rate Testing of 20% Cold-Worked Type 316 Stainless Steel Fast Reactor Cladding. NUCL TECHNOL 2017. [DOI: 10.13182/nt83-a33302] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]

Mast PK, Scott JH. An Analysis of Transient Overpower Accidents in the Fast Test Reactor Using the Los Alamos Failure Model. NUCL TECHNOL 2017. [DOI: 10.13182/nt79-a32371] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]

Ingman D, Reznik L. A Dynamic Reliability Model for Damage Accumulation Processes. NUCL TECHNOL 2017. [DOI: 10.13182/nt86-a33841] [Citation(s) in RCA: 7] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]

ARAI S, MURABAYASHI H, TANABE A, YOSHIDA K, SUMIDA S. Failure Correlation for Zircaloy-2 Fuel Cladding under High Temperature Transient Conditions. J NUCL SCI TECHNOL 1987. [DOI: 10.1080/18811248.1987.9735795] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/28/2022]

Analyses with the FSTATE code; fuel performance in destructive in-pile experiments. NUCLEAR ENGINEERING AND DESIGN 1983. [DOI: 10.1016/0029-5493(83)90064-x] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]

SHIMEGI N. FCI-related Material Movements under LOF-driven-TOP Accident Condition of LMFBR. J NUCL SCI TECHNOL 1980. [DOI: 10.1080/18811248.1980.9732545] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/28/2022]

Mattila L, Sairanen R, Stengȧrd JO. Probabilistic models for fuel rod puncturing in an LWR core during a LOCA. NUCLEAR ENGINEERING AND DESIGN 1976. [DOI: 10.1016/0029-5493(76)90009-1] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/27/2022]