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Journal Articles

Application of USV to marine monitoring after Fukushima Daiichi Nuclear Power Plant Accident and its applicability as a nuclear disaster prevention tool

Sanada, Yukihisa; Misono, Toshiharu; Shiribiki, Takehiko*

Kaiyo Riko Gakkai-Shi, 27(2), p.37 - 44, 2023/12

This paper summarizes the general situation of marine monitoring conducted after the Fukushima Daiichi Nuclear Power Plant accident, the experience of development and operation of USVs, and the possibility of applying unmanned vessels as a tool for nuclear disaster prevention in the future. 0.01 Bq/L or less for seawater and 10 Bq/L or less for seabed soil. Operational tests of three USVs have been continuously conducted for use in such environmental radiation monitoring. Development of these UAVs is underway with a view to utilizing them for seawater sampling, direct measurement of the seafloor soil surface layer, and seafloor soil sampling, depending on their performance. It is necessary to promote the development of USVs for future nuclear power plant accidents.

Journal Articles

Influence of artificial radionuclide deposited on a monitoring post on measured value of ambient dose rate

Hiraoka, Hirokazu; Hokama, Tomonori; Munakata, Masahiro

Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 5 Pages, 2019/05

Neighboring inhabitants of nuclear facilities must evacuate according to an ambient dose rate at a nuclear accident. The evacuation is judged by the measured value by monitoring posts (MPs). However, if the measured value increase by artificial radionuclide deposited to MP, it is considered that the dose rate of the surrounding environment is overestimated. The purpose of this research is to evaluate exactly the dose rate even if the radionuclide deposit to the MP, in order to adequately evacuate inhabitants. Just a MP and horizontal ground was simulated. To calculate ambient dose rates from the roof surface of MP and ground surface, Monte Carlo calculation was done. And, it was obtained that the ratio which the dose rate from the roof account for sum of two these dose rates. According to the result, the ratio was 42%. It suggested that the radionuclide could increase the measured value. However, because simulated system was simple, it is considered that the ratio was overestimated.

Journal Articles

Units of radiation (radioactivity)

Takahashi, Fumiaki

Genshiryoku No Ima To Ashita, p.109 - 111, 2019/03

The Atomic Energy Society of Japan has planned to publish a document for public, entitled "Current and tomorrow of atomic energy, -Experiences from the accident at the Tokyo Electronic Power Company Fukushima Dai-ichi NPPs-". The documents give us basics and usages of radiations, in addition to nuclear power plants and the accident at TEPCO Fukushima Dai-ichi NPPs. This manuscript explains physical quantities (e.g., absorbed dose), protection quantities and operational quantities that are used for radiation measurement and protection. The unit of radioactivity is also explained, because radioactivity is measured for work places in a radiation facility for internal exposure protection. In addition, radiation dose constants that relate radiation dose to the activity are also introduced, as useful radiation units for radiation protection.

Journal Articles

Introduction to radiation physics; Third revised edition

Tada, Junichiro*; Nakashima, Hiroshi; Hayano, Ryugo*; Kobayashi, Hitoshi*; Asano, Yoshihiro*

Wakariyasui Hoshasen Butsurigaku; Kaitei 3-Han, 305 Pages, 2018/03

This book is an introduction to radiation physics. Under the concept of "linking physics of high school and radiation physics" for readers with high school graduation degree, we are doing simple commentary on the basis of qualitative explanation as much as possible. This book begins with "What is Radiation Physics", and consists of 12 chapters, including introductory special relativity, introductory quantum theory, structures of atoms and nuclei, radiations, radioactivity, interactions between radiation and matter, accelerators, radiation dose and so on.

JAEA Reports

Determination of neptunium in neptunium-uranium-plutonium mixed oxide fuel by spectrophotometry.

; ; ; ; ; *; *

JNC TN8400 2001-026, 29 Pages, 2001/12

JNC-TN8400-2001-026.pdf:0.99MB

The measurement condition by spectrophotometry was evaluated to measure Np content in MOX fuel containing Np. The Np concentration was obtained by measuring the 727nm absorption peak, after the valence of Np in the sample solution was adjusted to the Np(Ⅳ). The calibration curve showed the linearity up to Np concentration 0.8mg/ml. Though Pu and U quantity were respectively added to the Np solution to 30 times and 60 times of Np concentration, there was no effect to the Np analysis. By using this method, relative standard deviation (RSD) of the analyzed values of Np content for 2%Np - MOX fuel was about 4%. In addition, It was confirmed that the Np content could be measured without separating Np from Pu and U. This method can be sufficiently applied as a quick simple method to analyze Np content in MOX fuel containing Np.

JAEA Reports

The Primary evaluation of the impacts of naturaI phenomena on the safety functions of the geological disposal system; An Example study on site generic phase

Makino, Hitoshi; ; Miyahara, Kaname

JNC TN8400 2000-033, 74 Pages, 2000/11

JNC-TN8400-2000-033.pdf:9.19MB

Natural phenomena is one of the potential factors perturbing the long-term stability of the geological environment, and for natural phenomena, it is necessary to consider uncertainties relevant to time, frequency and effect. Therefore it will be important to have information about the potential impacts of natural phenomena on the safety functions of geological disposal system in the future by assuming that natural phenomena perturbs the safety functions of the geological disposal system. In this report, we have considered 4 natural phenomena, 'uplift, subsidence and denudation', 'climatic and sea-level changes', 'earthquakes and fault movement' and 'volcanism', which had been extracted by investigation in foreign countries and by considering the characteristics of Japan as natural phenomena which may perturb the long-term stability of the geological environment. And we have considered mainly typical effects of naturaI phenomena on geological environment and investigated the typical impacts of those natural phenomena on the safety functions of the geological disposal system. On perturbation scenarios, the maximum of total doses have been less than regulatory guidelines in foreign countries in all situations except the cases assuming that a new fault, which causes significant pathway of groundwater flow and nuclide migration, intersects the waste packages. In the case, the maximum of total doses may reach the same level as regulatory guidelines in foreign countries or natural radiation exposure in Japan depending on fault generation time or grandwater flow rate through the fault. And, on isolation failure scenarios, it has been implied that nuclide mass/flux originated from geological disposal is comparable level with nuclide mass/flux in natural environment. These results could give useful information about the potential impacts of natural phenomena on the safety functions of geological disposal system, and also could show the potential importance of ...

JAEA Reports

None

*; *

JNC TJ7440 2000-005, 45 Pages, 2000/03

JNC-TJ7440-2000-005.pdf:2.72MB

no abstracts in English

JAEA Reports

Thermodynamic Date for Predicting Concentrations of Th(IV), U(IV), Np(IV), and Pu(IV) in Geologic Environments

Rai, D.*; Rao, L.*; Weger, H. T.*; Felmy, A. R.*; Choppin, G. R.*; Yui, Mikazu

JNC TN8400 99-009, 115 Pages, 1999/01

JNC-TN8400-99-009.pdf:5.19MB

This report provides thermodynamic data for predicting concentrations of Th(IV), U(IV), Np(IV), and Pu(IV) in geologic environments, and contributes to an integration of the JNC chemical thermodynamic database, JNC-TDB (previously PNC-TDB), for the performance analysis of geological isolation system for high-level radioactive wastes. Thermodynamic data for the formation of complexes or compounds with hydroxide, chloride, fluoride, carbonate, nitrate, sulfate and phosphate are discussed in this report. Where data for specific actinide(IV) species was lacking, the data were selected based on chemical analogy to other tetravalent actinides. ln this study, the Pitzer ion-interaction model is used to extrapolate thermodynamic constants to zero ionic strength at 25$$^{circ}$$C.

JAEA Reports

None

Tsujimura, Norio; Shinohara, Kunihiko; Momose, Takumaro

PNC TN8510 98-001, 13 Pages, 1998/07

PNC-TN8510-98-001.pdf:0.63MB

None

JAEA Reports

Measurement and evaluation of corrosion products deposition distribution in the experimental fast reactor JOYO

Aoyama, Takafumi; *; Sumino, Kozo; Saikawa, Takuya*

PNC TN9410 98-004, 74 Pages, 1997/12

PNC-TN9410-98-004.pdf:2.36MB

The Corrosion Product (CP) is the major radiation source in the primary cooling system of an LNFBR plant. It is important to characterize and predict the CP behavior to reduce the personnel exposure dose due to CP deposition. The CP measurement was carried out in the Experimental Fast Reactor JOYO during the 11th annual inspection period when the accumulated reactor thermal power reached about l43GWd. The CP deposition density was measured using a pure germanium detector. The plastic scintillation fiber (PSF) was applied for the gamma-ray dose rate distri bution measurement and compared with the thermoluminescence dosimeter (TLD). The major results obtained by the CP measurements in JOYO are the follows: (1)The major CP nuclides deposited in the primary cooling system are $$^{54}$$Mn and $$^{60}$$CO. $$^{54}$$Mn is the dominant isotope and it tends to deposit in the cold leg region. On the other hand, $$^{60}$$Co deposits mainly in the hot leg region. The deposition density of $$^{54}$$Mn is about seven times as much as that of $$^{60}$$Co in the cold leg region and twice in the hot leg region. (2)The deposition densities of $$^{54}$$Mn and $$^{60}$$Co, and the gamma-dose rate were decreased from the last data in the previous annual inspection period mainly due to the short operation time and the longer cooling time. (3)The continuous gamma-ray dose rate distribution up to 10m can be measured by using the PSF in a few minutes. The PSF is suitable to measure the gamma-ray dose rate distribution in the maintenance work area where it is narrow and the mixture of gamma-ray sources from primary pipings and components. The data base of detailed gamma-ray dose rate distribution was greatly extended by the PSF.

JAEA Reports

None

PNC TN8440 94-025, 112 Pages, 1994/03

PNC-TN8440-94-025.pdf:2.99MB

None

JAEA Reports

Demonstration study on shielding safety analysis code

Sawamura, Sadashi*

PNC TJ1600 94-002, 61 Pages, 1994/02

PNC-TJ1600-94-002.pdf:1.81MB

None

JAEA Reports

None

PNC TN8440 94-007, 106 Pages, 1993/12

PNC-TN8440-94-007.pdf:2.63MB

None

JAEA Reports

None

Kurosawa, Ryuhei*

PNC TJ1615 93-002, 13 Pages, 1993/03

PNC-TJ1615-93-002.pdf:0.35MB

no abstracts in English

JAEA Reports

None

PNC TJ1545 93-006, 224 Pages, 1993/03

PNC-TJ1545-93-006.pdf:10.3MB

no abstracts in English

JAEA Reports

None

;

PNC TN8440 92-039, 104 Pages, 1992/06

PNC-TN8440-92-039.pdf:2.58MB

None

JAEA Reports

None

; Maruo, Yoshihiro; ; Shinohara, Kunihiko

PNC TN8460 92-001, 65 Pages, 1992/03

PNC-TN8460-92-001.pdf:1.03MB

no abstracts in English

JAEA Reports

None

;

PNC TN8440 92-028, 115 Pages, 1992/03

PNC-TN8440-92-028.pdf:2.91MB

None

JAEA Reports

None

;

PNC TN8440 92-013, 104 Pages, 1991/12

PNC-TN8440-92-013.pdf:2.58MB

None

JAEA Reports

None

;

PNC TN8440 92-001, 107 Pages, 1991/09

PNC-TN8440-92-001.pdf:2.66MB

None

31 (Records 1-20 displayed on this page)