Mohamad Hairie Rabir

16 Questions 11 Answers 0 Followers

Questions related from Mohamad Hairie Rabir

How can we calculate the delayed neutron flux in an MCNP kcode simulation?

Is it possible to achieve this by combining flux tally and reaction rate cards?

25 June 2024 3,811 3 View

Can we establish a relationship between axial fuel burnup and core keff trend?

Can we establish a relationship between axial fuel burnup and core keff trend vs. average fuel burnup without simulating the actual axial burnup evolution of each individual fuel? To simplify...

21 June 2023 7,688 0 View

How reliable is the estimation of the assembly power peaking factor in a core calculation based on an infinite lattice calculation of the assembly?

If we do the core calculation on a homogenised fuel assembly, we can utilise a separate method to compute the assembly neutron flux and power distribution. How accurate would it be if we...

09 September 2021 3,794 1 View

Are there any experimental data on the graphitization effect of neutronics in HTGR?

I'm doing a neutronic simulation of a high-burnup, high-temperature graphite-moderated reactor. Is neutronics significantly affected if graphitization is neglected/considered? Note that I have...

23 September 2020 8,227 3 View

Is the change in the power density (Watt/cc) linearly proportional to the temperature (degree C)?

I use the MCNP code to calculate the power density of a single fuel block of the GT-MHR reactor, and I got about 20 Watt/cc with some pre-determined condition. I found that the average power...

23 March 2020 9,612 5 View

How to normalize MCNP tally if I use KCODE with SDEF initial source?

KCODE only normalized to power (with 1/keff) to obtain tally absolute value. I'm not sure if I use SDEF instead of KSRC in KCODE problem, do I normalize tally with source strength and the 1/keff...

04 August 2018 9,550 3 View

Example of MCNP input to tally time dependent neutron population?

I want to calculate neutron lifetime in a reactor. We can get prompt neutron removal time from 'kcode' calculation. In 'sdef' problem, we can use 'tme' card for time-dependent calculation. I have...

06 April 2016 1,841 1 View

Does the emitted beta energy spectrum in nuclear reaction 51V(n, beta)52Cr influenced by the neutron energy spectrum?

Self powered neutron detector with Vanadium-51 used to measure thermal neutron flux in our TRIGA MARK II reactor. Another question is, how to determine the conversion factor of current produced by...

03 February 2016 6,933 4 View

Does the prompt gamma spectrum in a reactor core significantly changed when it travel through certain medium?

I want to calculate the prompt gamma energy spectrum inside the reactor, in-core and out-core irradiation facility.

12 June 2015 9,425 6 View

What is the guideline in SSW and SSR in MCNP calculation?

I'm using MCNP ssw and ssr card for neutron penetration analysis in reactor shielding material. Several source surfaces is generated in sequences starting from the nearest surface from the core up...

29 October 2014 8,657 2 View

What is the neutronic benefit of a double layered burnable poison rod?

A long letdown curve is the ultimate objective of burnable poison rod especially for long cycle core design, or maybe for soluble boron free operation small modular reactor core (SBFO SMR) design...

12 March 2014 8,825 4 View

Which value of fission energy should be use in kcode tally normalization?

There are several value of fission energy from 180MeV to 200MeV, the same also for number of neutron/fission. These values produce quit significant differences in MCNP5/X final results. In MCNP5...

10 November 2013 7,604 0 View

Has anyone done a Gd rod composition analysis for PWR using MCNP?

I'm trying to see, the reactivity worth effect for Gd enrichment modification especially if we increase Gd157 and Gd155 percentage (since natural Gd currently used in PWR). Another thing is the...

15 July 2013 7,971 5 View

How do we measure the moderator temperature coefficient in PWR?

And how do we determine its relationship with critical boron concentration?

13 March 2013 9,907 6 View

How are we going to analyse the neutronics parameters of a liquid reactor core? Or a reactor core element that is continuously moving?

Example; LFTR or pebble bed reactor.

29 January 2013 5,320 3 View

How do I normalized MCNPX mesh tally (type 1: pedep) results to reactor power?

And what is the best unit to present the results? Watt/volume? Watt/gram? Or just watt?

21 September 2012 3,334 3 View