LOFT experimental support branch data abstract report: LOFT fuel rod thermocouple calibration test rod-RRF-A-8879

LOFT experimental support branch data abstract report: LOFT fuel rod thermocouple calibration test rod RRF-A-88102

10.2172/5475193 ◽

1979 ◽

Author(s):

C. W. Solbrig ◽

E. L. Tolman ◽

H. S. Selcho

Keyword(s):

Calibration Test ◽

Fuel Rod ◽

Experimental Support ◽

Thermocouple Calibration

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Assessing mindfulness: Experimental support for the discriminant validity of breath counting as a measure of mindfulness but not self-report questionnaires.

Psychological Assessment ◽

10.1037/pas0000957 ◽

2020 ◽

Vol 32 (12) ◽

pp. 1184-1190

Author(s):

Ben Isbel ◽

Kayla Stefanidis ◽

Mathew J. Summers

Keyword(s):

Discriminant Validity ◽

Self Report ◽

Experimental Support

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THE THERMAL-HYDRAULIC CALCULATION MODEL FOR GAS FLOW IN A FUEL ROD ASSEMBLY

Equipment ◽

10.1615/ihtc13.p7.70 ◽

2006 ◽

Author(s):

Benediktas B. Cesna

Keyword(s):

Gas Flow ◽

Calculation Model ◽

Hydraulic Calculation ◽

Fuel Rod

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SCALING OF TWO FLUID FLOW HEATED BY FUEL ROD

Proceeding of International Heat Transfer Conference 9 ◽

10.1615/ihtc9.4230 ◽

1990 ◽

Author(s):

S. Benedek

Keyword(s):

Fluid Flow ◽

Fuel Rod ◽

Two Fluid

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Reflection on the ductility of irradiated zircaloy-4 fuel rod cladding

Kerntechnik ◽

10.3139/124.110114 ◽

2010 ◽

Vol 75 (6) ◽

pp. 337-341

Author(s):

G. Sauer

Keyword(s):

Fuel Rod

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3D finite element analysis of a nuclear fuel rod with gap elements between the pellet and the cladding

Journal of Nuclear Science and Technology ◽

10.1080/00223131.2015.1037374 ◽

2015 ◽

Vol 53 (2) ◽

pp. 232-239 ◽

Cited By ~ 2

Author(s):

Chang-Hak Kang ◽

Sung-Uk Lee ◽

Dong-Yol Yang ◽

Hyo-Chan Kim ◽

Yong-Sik Yang

Keyword(s):

Finite Element Analysis ◽

Finite Element ◽

Nuclear Fuel ◽

Element Analysis ◽

3D Finite Element ◽

3D Finite Element Analysis ◽

Fuel Rod

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Incorporation of Taguchi approach with CFD simulations on laser welding of spacer grid fuel rod assembly

Materials Science and Engineering B ◽

10.1016/j.mseb.2021.115182 ◽

2021 ◽

Vol 269 ◽

pp. 115182

Author(s):

G. Satyanarayana ◽

K.L. Narayana ◽

B. Nageswara Rao

Keyword(s):

Laser Welding ◽

Taguchi Approach ◽

Cfd Simulations ◽

Spacer Grid ◽

Fuel Rod

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Enhancement of Heat Transfer Performance in Nuclear Fuel Rod Using Nanofluids and Surface Roughness Technique

Volume 8B: Heat Transfer and Thermal Engineering ◽

10.1115/imece2015-51476 ◽

2015 ◽

Cited By ~ 1

Author(s):

Kang Liu ◽

Titan C. Paul ◽

Leo A. Carrilho ◽

Jamil A. Khan

Keyword(s):

Heat Transfer ◽

Surface Roughness ◽

Heat Transfer Coefficient ◽

Transfer Coefficient ◽

Nuclear Fuel ◽

Three Dimensional ◽

Pressurized Water ◽

Bulk Fluid ◽

Fuel Rod ◽

Dimensional Surface

The experimental investigations were carried out of a pressurized water nuclear reactor (PWR) with enhanced surface using different concentration (0.5 and 2.0 vol%) of ZnO/DI-water based nanofluids as a coolant. The experimental setup consisted of a flow loop with a nuclear fuel rod section that was heated by electrical current. The fuel rod surfaces were termed as two-dimensional surface roughness (square transverse ribbed surface) and three-dimensional surface roughness (diamond shaped blocks). The variation in temperature of nuclear fuel rod was measured along the length of a specified section. Heat transfer coefficient was calculated by measuring heat flux and temperature differences between surface and bulk fluid. The experimental results of nanofluids were compared with the coolant as a DI-water data. The maximum heat transfer coefficient enhancement was achieved 33% at Re = 1.15 × 105 for fuel rod with three-dimensional surface roughness using 2.0 vol% nanofluids compared to DI-water.

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