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Journal Articles
Article Type: Research-Article
J. Pressure Vessel Technol. June 2023, 145(3): 031302.
Paper No: PVT-21-1199
Published Online: March 20, 2023
Journal Articles
Article Type: Research-Article
J. Pressure Vessel Technol. June 2023, 145(3): 031401.
Paper No: PVT-21-1023
Published Online: March 20, 2023
Image
in Critical Evaluation of a Novel Analysis Technique for Assessment of Printed Circuit Heat Exchangers in High-Temperature Nuclear Service
> Journal of Pressure Vessel Technology
Published Online: March 20, 2023
Fig. 1 Two-step analysis methodology of Shaw et al.—replace channeled core by elastic orthotropic solid core for PCHE global analysis followed by local submodel EPP analysis with detailed channel geometry and thermomechanical loading [ 4 ] More
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in Critical Evaluation of a Novel Analysis Technique for Assessment of Printed Circuit Heat Exchangers in High-Temperature Nuclear Service
> Journal of Pressure Vessel Technology
Published Online: March 20, 2023
Fig. 2 Total strain along the length of 2 × 2 counterflow submodel at center shown in Fig. 1 for the Time Step II of the 5th cycle More
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in Critical Evaluation of a Novel Analysis Technique for Assessment of Printed Circuit Heat Exchangers in High-Temperature Nuclear Service
> Journal of Pressure Vessel Technology
Published Online: March 20, 2023
Fig. 3 V-notched bar model (Model I) under tension for global and submodel local analyses More
Image
in Critical Evaluation of a Novel Analysis Technique for Assessment of Printed Circuit Heat Exchangers in High-Temperature Nuclear Service
> Journal of Pressure Vessel Technology
Published Online: March 20, 2023
Fig. 4 Equivalent total strain along V-notch root from global and submodel EPP analyses: ( a ) coarse global and refined submodel (inconsistent) mesh (Model I-Case I) and ( b ) consistent global and submodel fine (converged) mesh (Model I-Case II); D is V-notch bar width/depth More
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in Critical Evaluation of a Novel Analysis Technique for Assessment of Printed Circuit Heat Exchangers in High-Temperature Nuclear Service
> Journal of Pressure Vessel Technology
Published Online: March 20, 2023
Fig. 5 Single channel block global model with coarse mesh and submodel with refined mesh for EPP (inconsistent mesh Model II-Case I) analysis More
Image
in Critical Evaluation of a Novel Analysis Technique for Assessment of Printed Circuit Heat Exchangers in High-Temperature Nuclear Service
> Journal of Pressure Vessel Technology
Published Online: March 20, 2023
Fig. 6 Equivalent total strain along channel corner from global coarse mesh and submodel refined mesh (inconsistent mesh Model II-Case I) EPP analysis More
Image
in Critical Evaluation of a Novel Analysis Technique for Assessment of Printed Circuit Heat Exchangers in High-Temperature Nuclear Service
> Journal of Pressure Vessel Technology
Published Online: March 20, 2023
Fig. 7 Equivalent total strain along channel corner from global model and submodel with consistent refined mesh for (Model II-Case II) EPP analysis More
Image
in Critical Evaluation of a Novel Analysis Technique for Assessment of Printed Circuit Heat Exchangers in High-Temperature Nuclear Service
> Journal of Pressure Vessel Technology
Published Online: March 20, 2023
Fig. 8 Single channel block model with orthotropic solid coarse mesh for global elastic analysis and refined mesh submodel with detailed channel geometry and pressure loading for (Model II-Case III) EPP analysis More
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in Critical Evaluation of a Novel Analysis Technique for Assessment of Printed Circuit Heat Exchangers in High-Temperature Nuclear Service
> Journal of Pressure Vessel Technology
Published Online: March 20, 2023
Fig. 9 Equivalent total strains along channel corner from Model II-Cases I to III submodel analyses More
Image
in Critical Evaluation of a Novel Analysis Technique for Assessment of Printed Circuit Heat Exchangers in High-Temperature Nuclear Service
> Journal of Pressure Vessel Technology
Published Online: March 20, 2023
Fig. 10 Laboratory scaled PCHE model (Model III) dimension details More
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in Critical Evaluation of a Novel Analysis Technique for Assessment of Printed Circuit Heat Exchangers in High-Temperature Nuclear Service
> Journal of Pressure Vessel Technology
Published Online: March 20, 2023
Fig. 11 PCHE loading histories prescribed in the analysis: ( a ) channel pressure history, ( b )channel fluid temperature history, and ( c ) average temperature profile for global analysis of the PCHE core, and hot and cold temperatures for submodel analysis More
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in Critical Evaluation of a Novel Analysis Technique for Assessment of Printed Circuit Heat Exchangers in High-Temperature Nuclear Service
> Journal of Pressure Vessel Technology
Published Online: March 20, 2023
Fig. 12 PCHE channeled coarsely meshed global model and refined mesh submodel for Model III-Case I EPP analysis More
Image
in Critical Evaluation of a Novel Analysis Technique for Assessment of Printed Circuit Heat Exchangers in High-Temperature Nuclear Service
> Journal of Pressure Vessel Technology
Published Online: March 20, 2023
Fig. 13 PCHE orthotropic solid core coarsely meshed global model and channeled refined mesh submodel for inconsistent mesh Model III-Case II EPP analysis More
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in Critical Evaluation of a Novel Analysis Technique for Assessment of Printed Circuit Heat Exchangers in High-Temperature Nuclear Service
> Journal of Pressure Vessel Technology
Published Online: March 20, 2023
Fig. 14 Temperature profiles from the PCHE global thermal analyses at the end of the dwell time (time-step—III in Fig. 11 ): ( a ) Model III-Case I and ( b ) Model III-Case II More
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in Critical Evaluation of a Novel Analysis Technique for Assessment of Printed Circuit Heat Exchangers in High-Temperature Nuclear Service
> Journal of Pressure Vessel Technology
Published Online: March 20, 2023
Fig. 15 Temperature profiles from the submodel thermal analyses at the end of the dwell time (time-step—III in Fig. 11 ): ( a ) Model III-Case I and ( b ) Model III-Case II More
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in Critical Evaluation of a Novel Analysis Technique for Assessment of Printed Circuit Heat Exchangers in High-Temperature Nuclear Service
> Journal of Pressure Vessel Technology
Published Online: March 20, 2023
Fig. 16 Equivalent total strains along channel corner of submodel at the end of dwell period of the 5th cycle from the Model III-Case I and II analyses More
Image
in Critical Evaluation of a Novel Analysis Technique for Assessment of Printed Circuit Heat Exchangers in High-Temperature Nuclear Service
> Journal of Pressure Vessel Technology
Published Online: March 20, 2023
Fig. 17 Equivalent total strains along channel corner of submodel for 5 cycles from the Model III-Case I and II analyses More
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in Experimental and Numerical Research on Fluid Dynamic Interaction Effects of Reciprocating Pump–Pipeline System
> Journal of Pressure Vessel Technology
Published Online: March 20, 2023
Fig. 1 Schematic diagram of the testing platform: ① reservoir; ② suction pipe; ③ reciprocating pump; ④discharge pipe; ⑤ flow control valve; ⑥ data acquisition equipment; and ⑦ pressure sensor More