An overview on neutronic simulation schemes for reactor transient and safety analysis Anurag GuptaK. Umasankari Review 03 July 2017 Pages: 83 - 98
Production of radioisotopes Sm153 and Lu177 in Dhruva A. MishraJ. KumarSujay Bhattacharya Review 22 June 2017 Pages: 99 - 108
Application of best estimate thermal hydraulic code for safety analysis of high flux research reactor Samiran SenguptaVijay K. VeluriS. Bhattacharya Original, Research 20 June 2017 Pages: 109 - 117
Integrated modeling of postulated rod drop incident in a PHWR Vivek A. KaleK. ObaidurrahmanAvinash J. Gaikwad Original Research 26 June 2017 Pages: 119 - 126
Estimation of argon activation in HFRR pool water and primary coolant system Manoj Kumar HansdaShaji MammenSujay Bhattacharya Original Research 21 June 2017 Pages: 127 - 131
NEMHEX solution of benchmark problems on thermal and fast breeder reactor cores with hexagonal lattice Tej SinghParitosh PandeyTanay Mazumdar Original Research 22 June 2017 Pages: 133 - 139
Results of two-dimensional hexagonal dynamic benchmark problems solved using diffusion kinetic code Tej SinghTanay MazumdarParitosh Pandey Original Research 03 July 2017 Pages: 141 - 147
Thermal neutron flux measurements in self-serve and tray rod facilities of Dhruva reactor Y. S. RanaAbhishek MishraRanjit Sharma Original Application 21 June 2017 Pages: 149 - 166