Optimization of the Nodalization of Nuclear System Thermal-Hydraulic Code Applied On PKL Benchmark

2021 ◽  
Author(s):  
Hong Xu ◽  
Aurelian Florin Badea ◽  
Xu Cheng
Keyword(s):  
Nuclear System

Abstract see the manuscript

Thermal equilibrium of the nuclear system in theCa40(35 MeV/nucleon)+40Ca reaction

1994 ◽  
Vol 50 (5) ◽  
pp. 2614-2617 ◽  
Author(s):  
Sa Ben-Hao ◽  
Wang Rui-Hong ◽  
Zhang Xiao-Ze ◽  
Zheng Yu-Ming ◽  
Lu Zhong-Dao
Keyword(s):  
Thermal Equilibrium ◽  
Nuclear System

scholarly journals The Performance of the TCS 670-B Turbine in the Closed Cycle Test Facility at Fort Belvoir, Virginia

1971 ◽  
Author(s):  
G. B. Manning
Keyword(s):  
United States ◽  
Complete System ◽  
The United States ◽  
Test Facility ◽  
Nuclear System ◽  
Closed Cycle ◽  
Corps Of Engineers ◽  
Turbine Performance ◽  
Compressor Performance

The design of the first compact AK Process Nuclear system in the United States was performed under the auspices of the Corps of Engineers. U. S. Army, Fort Belvoir, Va. Taking into account that there was virtually nothing on the shelf that could be used, and realizing that the feasibility of such a system first had to be established, demonstration models were built for the various subsystem components which were to eventually go into the complete system. The last and final turbine-compressor set tested as a backup unit for this program was the TCS 670-B. This paper reports the turbine performance obtained from this machine when tested in the Closed Cycle Test Facility (APCEF) at Fort Belvoir, Va.. in 1969. The compressor performance is not included.

A Review of Alloy 800H for Applications in the Gen IV Nuclear Energy Systems

2010 ◽  
Author(s):  
Weiju Ren ◽  
Robert Swindeman
Keyword(s):  
Research And Development ◽  
Environmental Effect ◽  
Nuclear Energy ◽  
Energy Systems ◽  
Extensive Review ◽  
Nuclear System ◽  
Alloy 800H ◽  
Aging Resistance ◽  
Gen Iv ◽  
Data Requirements

Alloy 800H is currently under consideration for applications in the Next Generation Nuclear Plant at operational temperatures above 750°C. To provide supporting information in this paper at the attempt to facilitate the consideration, service requirements of the nuclear system for structural materials is first described; and then an extensive review of Alloy 800H is given on its codification with respect to development and research history, mechanical behavior and design allowables, metallurgical aging resistance, environmental effect considerations, data requirements and availability, weldments, as well as many other aspects relevant to the intended nuclear application; an finally further research and development activities to support the materials qualification are suggested.

Optimization of a recompression supercritical nitrous oxide and helium Brayton cycle for space nuclear system

Energy ◽  
2021 ◽  
pp. 123023
Author(s):  
Xinyu Miao ◽  
Haochun Zhang ◽  
Wenbo Sun ◽  
Qi Wang ◽  
Chenxu Zhang
Keyword(s):  
Nitrous Oxide ◽  
Brayton Cycle ◽  
Nuclear System

Identification of stochastic neutron pulse signal of 252Cf nuclear system based on Elman neural network

2011 ◽  
Vol 23 (8) ◽  
pp. 2224-2228
Author(s):  
冯鹏 Feng Peng ◽  
刘思远 Liu Siyuan ◽  
米德伶 Mi Deling
Keyword(s):  
Neural Network ◽  
Pulse Signal ◽  
Neutron Pulse ◽  
Nuclear System ◽  
Elman Neural Network
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