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CALCULATION OF RADIATION PRODUCTION OF HIGH SPECIFIC ACTIVITY ISOTOPES 192Ir AND 60Co
Zhou Quan, Zhong Wenfa, Xu Xiaolin
CHINESE JOURNAL OF COMPUTATIONAL PHYSICS    1997, 14 (S1): 684-686.  
Abstract187)      PDF (127KB)(960)      
The high specific activity isotopes:192Ir and 60Co in the high neutron flux reactor are calculated with the method of reactor physics.The results of calculation are analyzed in two aspects:the production of isotopes and the influence to parameters of the reactor,and hence a better case is proposed as a reference to the production.
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CALCULATING ANALYSIS FOR THE MONITOR HOLES IN THE REACTOR
Zhong Wenfa, Zhou Quan
CHINESE JOURNAL OF COMPUTATIONAL PHYSICS    1997, 14 (S1): 540-541,539.  
Abstract246)      PDF (131KB)(967)      
Calculating model and method for the reactor physics design of the disposition of monitor holes are presented.The calculated results with this model show that the disposition of monitor holes increases the neutron flux andγflux out of the containment and concrete shell,and their effects in the shielding design should be accounted for.
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THE APPLICATION OF SIMULATION OF PEBBLE FLOW IN REACTOR PHYSICS FOR HTR
Zhong Wenfa, Jing Xingqing, Luo Jingyu, Li Shilin
CHINESE JOURNAL OF COMPUTATIONAL PHYSICS    1995, 12 (3): 325-329.  
Abstract235)      PDF (351KB)(1178)      
A calculational method is presented about the simulation of flow pattern of fuel elements in the physics calculation for Pebble Bed HTR. Then detailed calculation on 10MW HTR is described along with comparison of its results with that of a simplified computation without close simulation of the flow pattern of fuel elements in the reactor core.
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METHOD OF USING THE PROGRAMS WITH RECTANGULAR MESHES FOR COMPUTATION OF HTGR WITH PEBBLE BED FLOW
Jing Xingqing, Zhong Wenfa
CHINESE JOURNAL OF COMPUTATIONAL PHYSICS    1995, 12 (1): 95-101.  
Abstract183)      PDF (427KB)(935)      
Descriptions are on situations about the fuel ball flow in curvilineal channel of High Temperature Gas Pebble Bed Reactor, and on the method of solving that problem by using the programs with rectangular meshes. This method has been used for the physical design of HTR-10MW Test Module and can be spread over other problems with curvilineal meshes.
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A EFFECTIVE METHOD OF BURNUP CALCULATION
Zhong Wenfa, Luo Jingyu, Zhang Ruiyin
CHINESE JOURNAL OF COMPUTATIONAL PHYSICS    1992, 9 (S1): 583-586.  
Abstract279)      PDF (304KB)(1078)      
A method of burnup calulation is introduced in calculation of reactor physic in this paper. Burnup calculation is completed by interpolation table of macroscopic cross section vs burnup, interpolated method and solving diffusion equation. The calculated result compared with shearon Harri s's result is satisfied. The method has characteristic of use friendly, less calculated time and occuracy demand. Now it is used in the practical calculation of reactor physic. A effective tool is provided for engineering design.
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