Extension of CASCADE.04 to estimate neutron fluence and dose rates and its validation

Kumawat, H.; Kumar, Vinod; Srinivasan, P.

doi:10.1007/s12043-009-0053-4

Cited by 8 publications

(2 citation statements)

References 6 publications

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“…[19]. The code was further developed for the Neutron shielding and dosimetry applications [20]. The code can be used for single nucleus interaction in basic reaction studies and can be invoked for the thick target simulation during the transport.…”

Section: Description Of Moncmentioning

confidence: 99%

Accelerator Based Production of $^{225}$Ac for Cancer Treatment

Kumawat,

Suryanarayana

2020

Preprint

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Targeted Alpha Therapy potentially offers a more specific action in killing tumor cells and less damage to neighbouring normal cells compared to β-emitters. 225 Ac along with three other αemitting daughter nuclei 221 Fr, 217 At and 213 Po have significant potency for clinical use. Monte carlo simulation has been carried out using MONC code for production routes of 225 Ac for its possible generation using proton accelerators with Thorium-232 and Radium-226 targets. All the calculations has been carried out using global model parameters without adjusting for individual target. The study reveals that proton beam of 20-30MeV energy with 5µA current on radium-226 target can give rise to 1Ci of 225 Ac activity in a week of irradiation. Thorium irradiation at low proton energy produces smaller 225 Ac activity but one can benefit from high current, stable proton accelerators. Proton energy of 100MeV or above with hundreds of µA current can produce reasonable 225 Ac activity for practical use. However, the contamination of other co-produced radioisotopes is much less at low proton energy hence low energy high current proton accelerators are also viable alternative to generate Actinium-225 radio isotope.

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Section: Description Of Moncmentioning

confidence: 99%

Accelerator Based Production of $^{225}$Ac for Cancer Treatment

Kumawat,

Suryanarayana

2020

Preprint

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“…[7]. The code was further developed for the Neutron shielding and dosimetry applications and published [16]. The high energy part of this code can be used for single nucleus interaction in basic reaction studies and can be invoked for the thick target simulation during the transport.…”

Section: Construction Of Geometrymentioning

confidence: 99%

Status and Scope of MONC Transport Code

Kumawat,

Venkata

2020

Preprint

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MOnte-carlo Nucleon transport Code (MONC) for nucleon transport is being developed for several years. Constructive Solid Geometry concept is applied with the help of solid bodies. Union, subtraction and intersection Boolean operations are used to construct heterogeneous zones. Scaling, rotation, and translation operation of the basic bodies are allowed to construct more complex zones. Module of repetitive structure for lattice, core calculations in reactor and detector simulation is developed. Graphical User Interface along with visualization tools is developed to make input, construction and display of geometry, and analysis of output data. Low energy neutron transport module is developed using continuous linearly interpolable point neutron cross section data below 20MeV neutron energy. The code is benchmarked for simulation of accelerator driven sub-critical system, neutron shielding, heat and neutron flux distribution and keff of the critical assemblies. It is observed that results of keff are in agreement within ∼ 3mk with experimental results of critical assemblies as well as the values obtained from MCNP.

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