Perspectives on nuclear data for advanced reactor design and analysis

Author:

Kannan Umasankari

Publisher

Springer Science and Business Media LLC

Subject

General Engineering

Reference20 articles.

1. Cullen DE (2000) PREPRO2000, 2000. ENDF/B Preprocessing codes. IAEA-NDS-39, Rev. 10, April 2000

2. Deo K, Mallick AK, Chachra S, Samanta S, Kolekar RV, Tripathi M, Kumar R, Rasheed KK, Kannan U (2017) Neutron spectrum measurement in AHWR-critical facility, national symposium on advances in reactor physics (ARP2017) fission reactors- now and beyond, DAE Convention Centre, Mumbai, 6–9 Dec 2017

3. Dwivedi DK, Gupta A, Krishnani PD (2010) Challenges in core reactivity management and control optimization in physics design of Compact High Temperature Reactor. BARC Newsl 317:22–28

4. EXFOR (2020). http://www-nds.iaea.org/exfor/exfor.htm

5. Ganesan S (2004) New reactor concepts and new nuclear data needed to develop them. Invited Talk. In: Proceedings of the international conference on nuclear data for science and technology, ND2004, Santa Fe, New Mexico, USA, 26 September–1 October 2004, American Institute of Physics (AIP) Conference Proceedings CP 769, May 2005, pp 1411–1416

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