Effect of coolant channel width on group constants and multiplication factor of research reactors using MTR type low enriched uranium fuel

Annals of Nuclear Energy

Volumn 29, Issue 4, 2002, Pages 477-488

  Aslam, ^a   Ahmad, N ^a  

^a PAKISTAN INSTITUTE OF ENGINEERING AND APPLIED SCIENCES   (Pakistan)

Author keywords

[No Author keywords available]

Indexed keywords

COOLANTS; DIFFUSION; NUCLEAR FUELS; OPTIMIZATION; URANIUM;

LOW ENRICHED URANIUM (LEU); MATERIAL TESTING REACTORS (MTR);

EXPERIMENTAL REACTORS;

EID: 0036489487     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0306-4549(01)00047-0     Document Type: Article

References (5)

1. Nuclear reactor core analysis code-CITATION
2. Pakistan research reactor-1
3. Reactor Physics Calculations and their experimental validation for conversion and upgrading of a typical swimming pool type research reactor
4. Solution of neutron spectrum adjustment problem in a typical MTR type research reactor