... environmental correction factor, F en , to account for EAF. NRC regulation (NUREG), NUREG/CR-6909 (NRC, 2013, “Effect of LWR Coolant Environments on the Fatigue Life of Reactor Materials,” U.S. Nuclear Regulatory Commission, Argonne, IL, Standard no. NUREG/CR-6909), presents the detail F en calculation formula...

... and digital evidence-related standards to the nuclear domain is being evaluated. Results of such evaluation are being considered in the three-dimensional and two-dimensional modeling of cybersecurity relevant assets. The development of the new IEC 63096, downstream standard of IEC 62645, will also support...

.... Editor: Leon Cizelj. 24 08 2017 26 11 2017 Nuclear engineering Reactor physics Standards Licensing Regulatory issues Codes Transport theory Burnup calculation is an important issue in reactor core calculation and analysis, and it is also the basis of fuel management...

...)). ANS standard N18.2-1973 [ 1 ] describes, as one example of a condition II event, a minor reactor coolant system leak which would not prevent orderly reactor shutdown and cooldown assuming makeup is provided by normal makeup systems...

...Asif Arastu; Yassin Hasan; Leon Cizelj; Jovica R. Riznic; Guoqiang Wang 09 01 2018 16 01 2018 Advanced reactors Nuclear engineering Nuclear safety Plant systems Thermal hydraulics Standards Licensing Regulatory issues Codes Plant construction Plant components Plant...

... details on BWR plant operation, see the U.S. Nuclear Regulatory Commission (USNRC) BWR Reactor Concepts Manual (available on the NRC public website) [ 1 ]. Nuclear safety Plant operations Standards Licensing Regulatory issues Codes Plant engineering Plant modifications Plant life cycle...

... and guidance are needed to be established by BAPETEN in order to complete the current regulations so that problems can all be anticipated. 13 09 2016 12 06 2017 Issues Standards Licensing Regulatory issues Codes Based on Indonesia Nuclear Energy Act of 1997 [ 1 ], any use...

.... Advanced reactors Fusion Engineering Nuclear engineering Research reactors Thermal hydraulics Standards Licensing Regulatory issues Codes Copyright © 2017 by ASME 2017 2332-8983/2017/3(4)/041009/13/ $25.00 ...

... others to do so, for United States government purposes. 29 09 2016 16 12 2016 Coupled codes Nuclear safety Thermal hydraulics Standards Licensing Regulatory issues Codes Security Because the nuclear power industry continually improves its designs, safety equipment...

... Advanced reactors Standards Licensing Regulatory issues Codes The HTTR [ 1 ] is a block-type HTGR with the outlet gas temperature of 950°C. It is difficult to insert all of the control rods simultaneously at the reactor scram under the full-power operation due to the high temperature...

... at 136°C. The criticality control rod positions are also calculated under the temperature condition at 136°C. Advanced reactors Research reactors Standards Licensing Regulatory issues Codes The HTTR [1] is a block-type HTGR. Since the first criticality was accomplished in 1998, many...

... system is to implement a short-/medium-term transient-level dynamics requiring fast sensor response, online measurement, and some nonlinearity features that are crucial for its control. The obtained results show that the TDR application on the OTSG is feasible at standard ambient temperature and pressure...