Measurement of leakage neutron flux from reactor tank surface of AHWR-critical facility

Author:

Deo KapilORCID,Mallick A.K.,Bhandari Deep,Kumar Rajeev,Kannan Umasankari

Publisher

Elsevier BV

Subject

General Physics and Astronomy

Reference9 articles.

1. Design and development of the AHWR - the Indian thorium fueled innovative nuclear reactor;Sinha;Nucl. Eng. Des.,2006

2. Critical Facility for lattice physics experiments for the Advanced Heavy Water Reactor and the 500MWe pressurized heavy water reactors;Raina;Nucl. Eng. Des.,2006

3. Reactor Physics Experiments at AHWR-Critical Facility, BARC Report;Deo,2022

4. IAEA Nuclear Energy Series, No. NP-T-3.11, Integrity of Reactor Pressure Vessels in Nuclear Power Plants: Irradiation Embrittlement Effects in Reactor Pressure Vessel Steels.

5. ASTM Standard E264-08(2013), Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Nickel.

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