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                             9 results found
no title author magazine year volume issue page(s) type
1 An overview on neutronic simulation schemes for reactor transient and safety analysis Gupta, Anurag
 2017
 6 2 p. 83-98
 article
2 Application of best estimate thermal hydraulic code for safety analysis of high flux research reactor Sengupta, Samiran
 2017
 6 2 p. 109-117
 article
3 Editorial Singh, Tej
 2017
 6 2 p. 79-81
 article
4 Estimation of argon activation in HFRR pool water and primary coolant system Hansda, Manoj Kumar
 2017
 6 2 p. 127-131
 article
5 Integrated modeling of postulated rod drop incident in a PHWR Kale, Vivek A.
 2017
 6 2 p. 119-126
 article
6 NEMHEX solution of benchmark problems on thermal and fast breeder reactor cores with hexagonal lattice Singh, Tej
 2017
 6 2 p. 133-139
 article
7 Production of radioisotopes Sm153 and Lu177 in Dhruva Mishra, A.
 2017
 6 2 p. 99-108
 article
8 Results of two-dimensional hexagonal dynamic benchmark problems solved using diffusion kinetic code Singh, Tej
 2017
 6 2 p. 141-147
 article
9 Thermal neutron flux measurements in self-serve and tray rod facilities of Dhruva reactor Rana, Y. S.
 2017
 6 2 p. 149-166
 article
                             9 results found
 
 Koninklijke Bibliotheek - National Library of the Netherlands