Useful tool for human life and industry; Irradiation facilities of cobalt-60 rays

Haruyama, Yasuyuki

Kigyo Sapoto Gumma, P. 13, 2004/04

Outline of cobalt-60 -ray facilities for radiation processing is described. It consists of characteristics of cobalt-60 source, components of the facility, and radiation safety systems. Typical products in -ray processing are also shown.

Decontamination factor of the commerciaI detergents for the skin (Part 3)

Miyabe, Kenjiro; Takasaki, Koji; Yasunaga, Hideo*; Izumi, Yuichi*

JNC TN8420 2000-007, 100 Pages, 2000/08

JNC-TN8420-2000-007.pdf:7.66MB

The commercial detergents, which are cleansing cream, shampoo, neutral detergent, etc., were examined in order to select the body cleaners that are substitutes for the titanium dioxide paste. JNC entrusted Japan Environment Research Corporation Limited with these examinations since 1997. In 1997 and 1998, the commercial detergents were examined for Ce-144, Cs-137 and Ru-106. In 1999, 22 detergents were examined for Co-60 from the result of the past examinations. In this examination, the radioactive solution of Co-60 was dropped on the pig-skin samples. These samples were washed with each detergent after 5 minutes and 40 minutes. The decontamination factors of detergents were estimated by the radioactive ratio of the samples before and after washing. As a result of this examination, the decontamination factors for Co-60 was the same as the decontamination factors for Ce-144 and Cs-137, and 11 detergents were nominated as the cleaner that have the decontamination factor more than that of titanium dioxide paste.

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 Mn and CO. Mn is the dominant isotope and it tends to deposit in the cold leg region. On the other hand, Co deposits mainly in the hot leg region. The deposition density of Mn is about seven times as much as that of Co in the cold leg region and twice in the hot leg region. (2)The deposition densities of Mn and 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.

None

PNC TJ8409 98-003, 62 Pages, 1997/03

PNC-TJ8409-98-003.pdf:3.14MB

None

Evaluation of value for hydrogen release from high-level liquid waste, 4; Hydrogen release rate for -ray radiolysis of simulated purex waste solutions

Miyata, Teijiro; Nakagiri, Naotaka*

Nihon Genshiryoku Gakkai-Shi, 39(12), p.1062 - 1068, 1997/00

https://doi.org/10.3327/jaesj.39.1062

no abstracts in English

Development of accurate CP distribution measurement FBR plant using a plastic scintillation fiber detector

Sumino, Kozo; Aoyama, Takafumi; Emoto, Takehiko

PNC TN9410 96-233, 27 Pages, 1996/08

PNC-TN9410-96-233.pdf:0.96MB

It is important to accurately evaluate Corrosion Products (CPs) behavior in a FBR plant to reduce the personnel exposure due to CP deposition. A series of measurements of the gamma-ray dose rate distribution has been carried out in the Experimental Fast Reactor JOYO to characterize the CP behavior in the primary coolant system. The Plastic Scintillation Fiber (PSF), which is a position sensitive radiation detector that can detect the radiation dose rate at the relevant position in the fiber, was introduced to upgrade the gamma-ray distribution measurement in JOYO. In order to apply the PSF for the JOYO environment, the specification of the fiber was modified to obtain a wide range of sensitivity from about 0.01mSv/h up to 10mSv/h. This range covers the gamma-ray dose rate in the JOYO primary coolant system. In higher gradients of dose rate distribution than that of the PSF's position resolution, the measured data were unfolded by using the response matrix with a successive approximation method to reproduce the narrow distribution. As a result of the study on PSF, the continuous gamma-ray dose rate distribution was able to be measured by PSF in a few minutes, whereas point data at 1 m intervals were laboriously obtained by a set of Thermo-luminescence Dosimeters (TLDs). It was confirmed that the measurement of CP behavior upgraded significantly by using a detailed gamma-ray dose rate distribution.

None

PNC TJ1603 96-003, 51 Pages, 1996/03

PNC-TJ1603-96-003.pdf:1.28MB

None

Effects of drying on desorption behavior of radionuclides adsorbed on a sand

Tanaka, Tadao

JAERI-Research 95-044, 21 Pages, 1995/06

JAERI-Research-95-044.pdf:0.79MB

no abstracts in English

Adsorption and desorption properties of radionuclides on source materials used for ground migration test

Tanaka, Tadao; Yamamoto, Tadatoshi; *

Nihon Genshiryoku Gakkai-Shi, 37(1), p.51 - 58, 1995/00

https://doi.org/10.3327/jaesj.37.51

no abstracts in English

Migration of cobalt-60 through aerated zone under discontinuous flow condition

Tanaka, Tadao; Yamamoto, Tadatoshi

Journal of Nuclear Science and Technology, 31(4), p.308 - 313, 1994/04

https://doi.org/10.3327/jnst.31.308

no abstracts in English