Questions related to Nuclear Safety
In the event like the Fukushima accident, if the turbine-driven pump fails, one can use accumulators to inject the store inventory into the SG for additional coping time. Why don't we do that?
Dissertation tackling nuclear law (nuclear safety and nuclear liability).
As same as the future of nuclear energy by dealing with topics such as nuclear waste management, nuclear security, non-proliferation as to how they have impacted in the development of nuclear energy and what what may be the future for nuclear energy law? Any recommendations as to where should the law evolve to have a more effective legal framework within this field?
Any recommendation, article would be welcome. Many thanks.
US nuclear utilities could start applying to the regulator from 2017 for operating licence extensions beyond 60 years. Staff at the Nuclear Regulatory Commission (NRC) say they are preparing for this.
In the reliability analysis of repairable and redundant safety systems someone needs to consider the effect of maintenance program. We are developing a Markov model for the ECCS system of a typical PWR reactor and for transition rates calculation we need the typical values of test interval and test duration for the ECCS system of a PWR nuclear reactor.
- To determine the neck thickness I need to calculate the forward range of electrons which might be produced by the Ion beam interactions.Since the range of Ion beam itself is in Microns,Is it safe to assume that if I keep my neck thickness around 2-3mm the electrons emitted in the forward direction won't leave the cup surface?.
I have assumptions to prove from real world datasets.
Assumption 1: In a small area (less than 1km x 1km), every locations have the same radiation / temperature.
I have this dataset from NRC Canada, and it seems the assumption is correct.
If the area is large (1km x 10km for example), does every location have the same radiation / temperature in that area? Yes or no. Any data to prove it?
I guess that there are few moments in a day when all locations share the same radiation values.
THe nuclear deals with most of the advanced countries are done in last couple of years for safety purpose i.e to enhance the power generation,power storage etc.People from various backgrounds have participated in that subject.It is purely civilian without damage to anybody with some errors.Nuclear diarmment was the main condition for this.
THe nuclear scientists, kindly say about its success rate.
Which type of cement, supplementary material & Nano particles can be proposed for making this concrete? What are test for nuclear shielding concrete, if there is any specific code book available? how i can measure the gamma radiation
In nuclear emergency many times it is difficult to predict when irradiation took place. in such scenario how gamma H2AX assay is useful for triage application. The foci readings are completely different even for small time gap.
Is adding Passive system with diversity high reliability in the safety systems the answer to sustained core decay heat removal for avoiding sever accident?
Is taxing the NPP operators with inaccurate severe accident analysis based SAMG justified?
What about the human reliability factor for SAMG implementation and success in preventing and mitigating sever accidents in new and existing NPPs?
I am working on the instability analysis of the Supercritical Water cooled Reactor(SCWR). My work is computational using MATLAB. I have developed the mathematical model for thermal hydraulic+fuel dynamics+neutronics for the analysis. If any one knows about the experimental data, or working on the experimental setup then please help. I am on my final stage of my Ph.D and I need to validate my computational work with experimental data. As far as, I know there are many journals available on natural circulation but very few are on forced circulation. Please suggest something. Thanks
I would like to know the equation related the neutron flux with the fluence rate in nuclear reactors.
Is there any reference data available for reliability and availability of GM based radiation survey meters which are used for routine survey purpose in industrial or medical institutions.
I'm studying the PARET but can't find the original manual or any primer/course/lecture on the internet. I have only been able to find the PARET/ANL user guide which is not very useful because I need something more detailed with input examples, etc.