Evaluation of biological dose rates around the ITER NBI ports by 2-D Sn/activation and 3-D Monte Carlo analyses

Sato, Satoshi; Iida, H.; Plenteda, Romano; Valenza, D.; Santoro, R.T.

doi:10.1016/s0920-3796(99)00100-3

Cited by 11 publications

(5 citation statements)

References 7 publications

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“…17. The ratios, which are used as the constant flux-to-dose conversion factor in the previous studies 3,4) as shown in Chap. I, are shown in Fig.…”

Section: Discussionmentioning

confidence: 99%

“…the NBI duct, an enormous number of histories and long calculation time is required to generate the weight window importance table in a single step. 2,3) This occurs because only 10 −7 to 10 −9 of neutrons born in the plasma can reach the target region. In this process, the target locations are sequentially moved from the inlet of the duct opening, Location A shown in Fig.…”

Section: Variance Reduction Methodsmentioning

confidence: 99%

“…3, in steps and the weight window importance table for each target location is generated. 3) When the neutron flux is obtained at the target location with good statistical error, e.g. less than 10%, the target location is moved to the next target location.…”

Section: Variance Reduction Methodsmentioning

confidence: 99%

“…2) Also in the previous studies, 3,4) the fast neutron fluxes were estimated by the Monte Carlo neutron trans-port calculation, and the decay gamma-ray dose rates were evaluated by multiplying the fast neutron fluxes with the constant flux-to-dose conversion factor based on the past experiences. In this case, the uncertainty due to the conversion factor is a critical issue.…”

Section: Introductionmentioning

confidence: 99%

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Evaluation of Shutdown Gamma-ray Dose Rates around the Duct Penetration by Three-Dimensional Monte Carlo Decay Gamma-ray Transport Calculation with Variance Reduction Method.

SATO¹,

Iida

Nishitani³

2002

J. Nucl. Sci. Technol.

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For the evaluation of gamma-ray dose rates around the duct penetrations after shutdown of nuclear fusion reactor, the calculation method is proposed with an application of the Monte Carlo neutron and decay gamma-ray transport calculation. For the radioisotope production rates during operation, the Monte Carlo calculation is conducted by the modification of the nuclear data library replacing a prompt gamma-ray spectrum with a decay gamma-ray spectrum. By multiplying each correction factor, which is ratio of the actual activation level after shutdown to the production rate during operation, with each decay gamma-ray flux due to each radioisotope, the decay gamma-ray dose rate is evaluated. In order to improve the statistical error, a variance reduction method is proposed by the application of the weight window importance technique and the specification of the decay gamma-ray generation location. We identify the cell producing the decay gamma-ray which can contribute the decay gamma-ray flux in evaluation locations, and forcibly terminate the gamma-ray transport calculation in the cells except for the identified cells. In order to validate the effectiveness of the method, shielding calculation for actual ITER (International Thermonuclear Experimental Reactor) configuration is performed, and small statistical errors below criteria are obtained. The effectiveness of the proposed method for ITER design analysis is demonstrated.

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“…17. The ratios, which are used as the constant flux-to-dose conversion factor in the previous studies 3,4) as shown in Chap. I, are shown in Fig.…”

Section: Discussionmentioning

confidence: 99%

Section: Variance Reduction Methodsmentioning

confidence: 99%

Section: Variance Reduction Methodsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

Evaluation of Shutdown Gamma-ray Dose Rates around the Duct Penetration by Three-Dimensional Monte Carlo Decay Gamma-ray Transport Calculation with Variance Reduction Method.

SATO¹,

Iida

Nishitani³

2002

J. Nucl. Sci. Technol.

Self Cite

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show abstract

“…In medical physics, S N methods are employed for radiation therapy treatment planning. They provide accurate simulations of neutron transport in tissues, aiding in the optimization of treatment delivery and dose calculations for cancer patients [12,13]. S N methods are also utilized to study neutral particle transport in astrophysical environments, such as neutron stars, supernovae, and other cosmic phenomena involving neutral particle interactions [14,15,16].…”

Section: Introductionmentioning

confidence: 99%

An Accurate and Efficient S N Method for Multigroup Neutron Transport Equations in Slab Geometry

Miao,

Jin

2023

Preprint

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Application of importances or weight windows in MCNP4C to a geometry similar to an ITER equatorial port

Wasastjerna¹

2008

Annals of Nuclear Energy

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Evaluation of biological dose rates around the ITER NBI ports by 2-D Sn/activation and 3-D Monte Carlo analyses

Cited by 11 publications

References 7 publications

Evaluation of Shutdown Gamma-ray Dose Rates around the Duct Penetration by Three-Dimensional Monte Carlo Decay Gamma-ray Transport Calculation with Variance Reduction Method.

Evaluation of Shutdown Gamma-ray Dose Rates around the Duct Penetration by Three-Dimensional Monte Carlo Decay Gamma-ray Transport Calculation with Variance Reduction Method.

An Accurate and Efficient S N Method for Multigroup Neutron Transport Equations in Slab Geometry

Application of importances or weight windows in MCNP4C to a geometry similar to an ITER equatorial port

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