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Reassessment of Internal Thyroid Doses to 1,080 Children Examined in a Screening Survey after the 2011 Fukushima Nuclear Disaster

Health physics (1958), 2020-01, Vol.118 (1), p.36

2020

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Development of a modified sum-peak method for activity determination of some gamma emitters

Nuclear instruments & methods in physics research. Section A, Accelerators, spectrometers, detectors and associated equipment, 2015-03, Vol.775, p.34-40

2015

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Numerical Simulation Based on Individual Voxel Phantoms for a Sophisticated Evaluation of Internal Doses Mainly From 131I in Highly Exposed Workers Involved in the TEPCO Fukushima Daiichi NPP Accident

Health physics (1958), 2019-05, Vol.116 (5), p.647

2019

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Effective dose conversion coefficients for radionuclides exponentially distributed in the ground

Radiation and environmental biophysics, 2012-11, Vol.51 (4), p.411-423

2012

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Biokinetic analyses of the latest actinide model for internal dose assessment after an accidental inhalation at a nuclear facility in Oarai, Japan

BIO Web of Conferences, 2019, Vol.14, p.2009

2019

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Radiological protection issues arising during and after the Fukushima nuclear reactor accident

Journal of radiological protection, 2013-09, Vol.33 (3), p.497-571

2013

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Implementation of the NCRP Wound Model for Interpretation of Bioassay Data for Intake of Radionuclides Through Contaminated Wounds

JOURNAL OF RADIATION RESEARCH, 2009, Vol.50 (3), p.267-276

Ishigure, Nobuhito

2009

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Distribution of thermal neutron flux around a PET cyclotron

Health physics (1958), 2011-05, Vol.100 Suppl 2, p.S60

2011

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Influence of short-lived radioiodines other than 131I on screening direct thyroid measurements with TCS-172 NAI(TL) survey meters

Radiation protection dosimetry, 2024-03, Vol.200 (3), p.315-321

2024

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Screening levels of TCS-172 NaI(Tl) survey meters used for direct thyroid measurements in nuclear disasters

Radiation protection dosimetry, 2023-10, Vol.199 (15-16), p.1989-1993

2023

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Biokinetic model analysis with DTPA administration for a case of accidental inhalation of actinides in Japan

Radiation protection dosimetry, 2023-10, Vol.199 (15-16), p.2025-2029

2023

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Dose Quantities Used in Radiological Protection for Internal Radiation Exposure

RADIOISOTOPES, 2013, Vol.62(7), pp.465-492

ISHIGURE, Nobuhito

2013

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The 45th Annual Meeting of Japan Health Physics Society

Japanese Journal of Health Physics, 2012, Vol.47(3), pp.163-163

ISHIGURE, Nobuhito

2012

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Calculation of Retention and Excretion of Some Selected Radionuclides after Acute Intake by Inhalation According to New ICRP Dose Estimation Models

Journal of nuclear science and technology, 1999-09, Vol.36 (9), p.830-838

ISHIGURE, Nobuhito

1999

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Calculation of the Absorbed Dose for the Overexposed Patients at the JCO Criticality Accident in Tokai-mura

JOURNAL OF RADIATION RESEARCH, 2001, Vol.42 (suppl), p.137-148

2001

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Measurement of the Induced Radionuclides in Production of Radiopharmaceuticals for Positron Emission Tomography (PET)

Journal of Nuclear Science and Technology, 2006-04, Vol.43 (4), p.348-353

2006

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A revised model for the deposition and clearance of inhaled particles in human extra-thoracic airways

Radiation protection dosimetry, 2014-01, Vol.158 (2), p.135-147

2014

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Dose assessment for workers involved in an internal contamination accident with Pu at JAEA’s Oarai R&D Center

BIO Web of Conferences, 2019, Vol.14, p.3014

2019

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Dose assessment for workers involved in an internal contamination accident with Pu at JAEA’s Oarai R D Center

BIO web of conferences, 2019-01, Vol.14, p.03014

2019

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Determination of Radionuclides Produced by Neutrons in Heavily Exposed Workers of the JCO Criticality Accident in Tokai-mura for Estimating an Individual’s Neutron Fluence

JOURNAL OF RADIATION RESEARCH, 2001, Vol.42 (suppl), p.117-128

2001

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Analytical Solution of the Compartment Model for Respiratory Tract Clearance Used in the New ICRP Lung Model

Journal of nuclear science and technology, 1996-02, Vol.33 (2), p.179-186

1996

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Report on the Expert Committee on Development and Utilization of Phantoms II

Japanese Journal of Health Physics, 2007, Vol.42(1), pp.38-52

2007

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Method of Dose Estimation Due to Radon Preface. 4. Application of New ICRP Respiratory Tract Model to Dosimetry of Radon Progeny

Hoken butsuri, 1999, Vol.34 (2), p.139-141

ISHIGURE, Nobuhito

1999

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内部被ばくの防護に用いられる線量

RADIOISOTOPES, 2013, Vol.62(7), pp.465-492

石榑, 信人

2013

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Calculation of Retention and Excretion of Some Selected Radionuclides after Acute Intake by Inhalation According to New ICRP Dose Estimation Models

Journal of nuclear science and technology, 1999-09, Vol.36 (9), p.830

ISHIGURE, Nobuhito

1999

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Reassessment of Internal Thyroid Doses to 1,080 Children Examined in a Screening Survey after the 2011 Fukushima Nuclear Disaster

Development of a modified sum-peak method for activity determination of some gamma emitters

Numerical Simulation Based on Individual Voxel Phantoms for a Sophisticated Evaluation of Internal Doses Mainly From 131I in Highly Exposed Workers Involved in the TEPCO Fukushima Daiichi NPP Accident

Effective dose conversion coefficients for radionuclides exponentially distributed in the ground

Biokinetic analyses of the latest actinide model for internal dose assessment after an accidental inhalation at a nuclear facility in Oarai, Japan

Radiological protection issues arising during and after the Fukushima nuclear reactor accident

Implementation of the NCRP Wound Model for Interpretation of Bioassay Data for Intake of Radionuclides Through Contaminated Wounds

Distribution of thermal neutron flux around a PET cyclotron

Influence of short-lived radioiodines other than 131I on screening direct thyroid measurements with TCS-172 NAI(TL) survey meters

Screening levels of TCS-172 NaI(Tl) survey meters used for direct thyroid measurements in nuclear disasters

Biokinetic model analysis with DTPA administration for a case of accidental inhalation of actinides in Japan

Dose Quantities Used in Radiological Protection for Internal Radiation Exposure

The 45th Annual Meeting of Japan Health Physics Society

Calculation of Retention and Excretion of Some Selected Radionuclides after Acute Intake by Inhalation According to New ICRP Dose Estimation Models

Calculation of the Absorbed Dose for the Overexposed Patients at the JCO Criticality Accident in Tokai-mura

Measurement of the Induced Radionuclides in Production of Radiopharmaceuticals for Positron Emission Tomography (PET)

A revised model for the deposition and clearance of inhaled particles in human extra-thoracic airways

Dose assessment for workers involved in an internal contamination accident with Pu at JAEA’s Oarai R&D Center

Dose assessment for workers involved in an internal contamination accident with Pu at JAEA’s Oarai R D Center

Determination of Radionuclides Produced by Neutrons in Heavily Exposed Workers of the JCO Criticality Accident in Tokai-mura for Estimating an Individual’s Neutron Fluence

Analytical Solution of the Compartment Model for Respiratory Tract Clearance Used in the New ICRP Lung Model

Report on the Expert Committee on Development and Utilization of Phantoms II

Method of Dose Estimation Due to Radon Preface. 4. Application of New ICRP Respiratory Tract Model to Dosimetry of Radon Progeny

内部被ばくの防護に用いられる線量

Calculation of Retention and Excretion of Some Selected Radionuclides after Acute Intake by Inhalation According to New ICRP Dose Estimation Models

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