Gamma-Ray Shielding Effectiveness of Some Alloys for Fusion Reactor Design

Singh, Vishwanath Pratap; Medhat, M.E.; Badiger, N.M.

doi:10.1007/s10894-014-9704-7

Cited by 7 publications

(5 citation statements)

References 23 publications

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“…The values obtained for ΣR/ρ by above equation are accurate within 10% of the experimental values investigated for aluminum, beryllium, graphite, hydrogen, iron, lead, oxygen, boron carbide etc. 5) The ΣR/ρ values of elements have been taken from Kaplan and Chilton. 6,7)…”

Section: ) Macroscopic Effective Neutron Removal Cross-sectionmentioning

confidence: 99%

“…The low atomic number elements are dominant conscientious for shielding of fast neutrons (2)(3)(4)(5)(6)(7)(8)(9)(10)(11)(12). Therefore, Table 1) is major reason for large variation of ΣR value for ordinary concrete sample.…”

Section: Macroscopic Effective Neutron Removal Cross-sectionmentioning

confidence: 99%

“…In present study, shielding parameters viz. mass attenuation coefficients, effective atomic numbers, fast neutron removal cross-section and exposure buildup factors were computed [3,[5][6][7]. The mass attenuation coefficients using XCOM program were also compared with MCNPX simulation results.…”

Section: Introductionmentioning

confidence: 99%

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Effect of Heat Treatment on Radiation Shielding Properties of Concretes

et al. 2018

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Background: Heat energy produced in nuclear reactors and nuclear fuel cycle facilities interactions modifies the physical properties of the shielding materials containing water content. Therefore, in the present paper, effect of the heat on shielding effectiveness of the concretes is investigated for gamma and neutron. The mass attenuation coefficients, effective atomic numbers, fast neutron removal cross-section and exposure buildup factors. Materials and Methods: The mass attenuation coefficients, effective atomic numbers, fast neutron removal cross-section and exposure buildup factors of ordinary and heavy concretes were investigated using NIST data of XCOM program and Geometric Progression method. Results and Discussion: The improvement in shielding effectiveness for photon and reduction in fast neutron for ordinary concrete was observed. The change in the neutron shielding effectiveness was insignificant. Conclusion: The present investigation on interaction of gamma and neutron radiation would be very useful for assessment of shielding efficiency of the concrete used in high temperature applications such as reactors.

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Section: ) Macroscopic Effective Neutron Removal Cross-sectionmentioning

confidence: 99%

Section: Macroscopic Effective Neutron Removal Cross-sectionmentioning

confidence: 99%

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Effect of Heat Treatment on Radiation Shielding Properties of Concretes

et al. 2018

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“…Vishwanath, Medhat, and Badiger have analyzed gamma‐ray shielding effect in ODS steels. They showed that ODS steels with low iron content reveal good shielding properties . Medhat and Wang have examined radiation shielding parameters of ODS steels such as effects of gamma ray, atomic numbers, electron densities, and mean free path.…”

Section: Introductionmentioning

confidence: 99%

“…They showed that ODS steels with low iron content reveal good shielding properties. 19 Medhat and Wang have examined radiation shielding parameters of ODS steels such as effects of gamma ray, atomic numbers, electron densities, and mean free path. They claimed ODS steels have good material properties in terms of photon interaction.…”

Section: Introductionmentioning

confidence: 99%

Evaluation of the radiation damage parameters of ODS steel alloys in the first wall of deuterium-tritium fusion-fission (hybrid) reactors

Tunç

Şahi̇n

2017

Int J Energy Res

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Summary One of the most important parameters in the design of the fusion‐fission hybrid reactor is the selection of the first wall material. Because the oxide dispersion‐strengthened (ODS) steel alloys have high temperature oxidation, high radiation resistance, good hardness, and corrosion resistance properties, they are thought first wall candidate materials for fusion and fission applications. The objective of this paper is to determine the best radiation damage parameters of various experimental and commercial ODS steels (namely, 12Y1, 12YWT, 1DS, IDK, Eurofer97, MA956, MA957, and PM 2000). Neutron spectrum and average neutron energy throughout blanket, displacement per atom, hydrogen and helium production, nuclear heating, and tritium breeding ratio were calculated by using Monte Carlo methods with Monte Carlo neutron‐photon transport code and nuclear libraries named as ENDF/B‐VI and CLAW‐IV. It is assumed that calculated reactor has been operated full power during a year and neutron wall load is 2.25 MW/m2 (1014 n/s). All investigated first wall materials should be replaced between 3.5 and 4 years. All investigated materials provide minimum required tritium breeding ratio value, and when considering all the calculations performed in this work, 1DS ODS steel is the most suitable first wall materials with respect to other investigated ODS steels.

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