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Journal Articles

Analysis of the relationship between ambient dose, ambient dose equivalent and effective dose in operational neutron spectra

Endo, Akira

Radiation Protection Dosimetry, 200(13), p.1266 - 1273, 2024/08

 Times Cited Count:0 Percentile:0.00(Environmental Sciences)

This study examines the relationship between ambient dose $$H^*$$, ambient dose equivalent $$H^*(10)$$, and effective dose for external neutron irradiation over 163 operational spectra from different workplaces. The results show that $$H^*$$ provides a reasonable estimate with a controlled margin, even if overestimated, to assess effective dose compared with $$H^*(10)$$, which can lead to a significant overestimation or underestimation of effective dose depending on the neutron spectra. The results highlight the limitations of $$H^*(10)$$ and the superiority of $$H^*$$ in estimating effective dose according to the requirements of the operational quantity, especially in environments with high-energy neutrons.

Journal Articles

Conceptual design of spectrum changeable neutron calibration fields in JAERI/FRS

Saegusa, Jun; Tanimura, Yoshihiko; Yoshizawa, Michio; Yoshida, Makoto

Radiation Protection Dosimetry, 110(1-4), p.91 - 95, 2004/09

 Times Cited Count:5 Percentile:28.05(Environmental Sciences)

For the accurate estimation of neutron dose equivalents, it is important to calibrate dosemeters in the field whose energy spectrum is similar to that in the workplace. For the purpose, studies are made toward the built of the spectrum changeable neutron calibration fields with the Van-de-Graff accelerator in the FRS in JAERI. The fields are produced by bombarding proton or deuteron beam from the accelerator to suitable targets surrounded by quasi-cylindrical moderators and absorbers of various materials. In the fields, neutron spectra with wide range energy index should be provided with sufficient fluence rate for the calibration of dosemeters. The objectives and conceptual design of the fields are discussed here, followed by the test simulation results of neutron spectra produced by various arrangements of a target and moderators.

Journal Articles

Neutron spectra and angular distributions of concrete-moderated neutron calibration fields at JAERI

Yoshizawa, Michio; Tanimura, Yoshihiko; Saegusa, Jun; Nemoto, Hisashi*; Yoshida, Makoto

Radiation Protection Dosimetry, 110(1-4), p.81 - 84, 2004/09

 Times Cited Count:3 Percentile:22.33(Environmental Sciences)

The facility of Radiation Standards (FRS) of JAERI has equipped with the concrete-moderated neutron calibration fields as simulated workplace neutron fields. The fields use an Am-Be (37GBq) neutron source placed in the narrow space surrounded by concrete wall and bricks to produce scattered neutrons. The neutron spectra of the fields were measured with Bonner multi-sphere spectrometer system (BMS), spherical recoil-proton proportional counters (RPCs), and a liquid scintillation counter (NE-213). The results were compared with each other, and the neutron spectra and the ambient dose equivalent rate, ${it H}$$$^{*}$$(10), were agreed well within the uncertainty. The angular distributions of neutron fluence were calculated by the MCNP-4B2 Monte Carlo code to obtain the reference personal dose equivalent rate, ${it H}$$$_{p}$$(10). The calculated results show that the scattered neutrons have a wide variety of incident angles. The reference ${it H}$$$_{p}$$(10) values considered the angular distribution were found to be 10-18% smaller than those without consideration.

Journal Articles

Dose evaluation in criticality accident conditions using transient critical facilities fueled with a fissile solution

Nakamura, Takemi*; Tonoike, Kotaro; Miyoshi, Yoshinori

Radiation Protection Dosimetry, 110(1-4), p.483 - 486, 2004/09

 Times Cited Count:2 Percentile:16.43(Environmental Sciences)

Dose measurement and evaluation technique in criticality accident conditions with a thermo luminescence dosimeter (TLD) was studied at the Transient Experiment Critical Facility (TRACY) of Japan Atomic Energy Research Institute (JAERI). The tissue absorbed dose can be derived from the ambient dose equivalent given by measurement with a TLD using the conversion factor given by computation. Using this technique, the neutron dose around the SILENE reactor of the Institute for Radioprotection and Nuclear Safety (IRSN) of France was measured in the Accident Dosimetry Intercomparison Exercise (June 10-21, 2002) organized by OECD/NEA and IRSN. In this exercise, the $$gamma$$ dose was also measured with a TLD. In this report, measurements and evaluation results at TRACY and SILENE are presented.

JAEA Reports

JAEA Reports

Experimental data on polyethylene shield transmission of quasi-monoenergetic neutrons generated by 43- and 68-MeV protons via $$^{7}$$Li(p,n) reaction

Nakao, Noriaki*; Nakashima, Hiroshi; Nakao, Makoto*; Sakamoto, Yukio; Nakane, Yoshihiro; ; Tanaka, Shunichi; Nakamura, Takashi*

JAERI-Data/Code 98-013, 46 Pages, 1998/03

JAERI-Data-Code-98-013.pdf:2.14MB

no abstracts in English

JAEA Reports

Experimental data on concrete shield transmission of quasi-monoenergetic neutrons generated by 43-and 68-MeV protons via the $$^{7}$$Li(p,n) reaction

Nakao, Noriaki*; Nakashima, Hiroshi; Sakamoto, Yukio; Nakane, Yoshihiro; Tanaka, Shunichi; ; Nakamura, Takashi*; Shin, Kazuo*;

JAERI-Data/Code 97-020, 46 Pages, 1997/06

JAERI-Data-Code-97-020.pdf:1.53MB

no abstracts in English

JAEA Reports

A Point kernel shielding code, PKN-HP, for high energy proton incident

JAERI-Data/Code 96-020, 45 Pages, 1996/06

JAERI-Data-Code-96-020.pdf:1.1MB

no abstracts in English

JAEA Reports

Experiments on iron shield transmission of quasi-monoenergetic neutrons generated by 43- and 68-MeV protons via the $$^{7}$$Li(P,n) reaction

; Nakao, Noriaki*; Tanaka, Shunichi; Nakamura, Takashi*; Shin, Kazuo*; Tanaka, Susumu; Meigo, Shinichiro; Nakane, Yoshihiro; Takada, Hiroshi; Sakamoto, Yukio; et al.

JAERI-Data/Code 96-005, 46 Pages, 1996/03

JAERI-Data-Code-96-005.pdf:1.54MB

no abstracts in English

JAEA Reports

PKN-H: A Point kernel shielding code for neutron source up to 400 MeV

; Sakamoto, Yukio; Tanaka, Shunichi

JAERI-Data/Code 95-004, 64 Pages, 1995/06

JAERI-Data-Code-95-004.pdf:1.55MB

no abstracts in English

Journal Articles

Basic physical data needed for dose evaluation

Sakamoto, Yukio; Tanaka, Shunichi; ; W.Pairsuwan*; Yoshizawa, Nobuaki*; ; Furihata, Shiori*; Uehara, Takashi*; Iwai, Satoshi*

JAERI-Conf 95-007, 0, p.48 - 56, 1995/03

no abstracts in English

JAEA Reports

Attenuation data of point isotropic neutron sources up to 400MeV in water, ordinary concrete and iron

; Tanaka, Shunichi; Sakamoto, Yukio; Nakane, Yoshihiro;

JAERI-Data/Code 94-003, 70 Pages, 1994/08

JAERI-Data-Code-94-003.pdf:3.31MB

no abstracts in English

JAEA Reports

Neutron shielding point kernel integral calculation code for personal computer: PKN-pc

; Sakamoto, Yukio; Nakane, Yoshihiro; ;

JAERI-Data/Code 94-004, 76 Pages, 1994/07

JAERI-Data-Code-94-004.pdf:2.26MB

no abstracts in English

JAEA Reports

JAEA Reports

Evaluation of fluence to dose equivalent conversion factors for high energy radiations, I; Preparation of code system and basic data

; Uehara, Takashi*; ; Iwai, Satoshi*; Tanaka, Shunichi

JAERI-M 92-126, 88 Pages, 1992/09

JAERI-M-92-126.pdf:1.91MB

no abstracts in English

JAEA Reports

JAEA Reports

17 (Records 1-17 displayed on this page)
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