Marine environmental assessment system of radionuclides around Japan

Kobayashi, Takuya; Togawa, Orihiko

Proceedings from the International Conference on Radioactivity in the Environment (CD-ROM), 4 Pages, 2002/09

A marine environmental assessment system STEAMER is developing for predicting the short-term (30days) dispersion and assessing the collective dose to the Japanese population due to radionuclides released to the ocean. The computer code system for short-term predictions of radionuclide dispersion is a combination of the Princeton Ocean Model (POM) for predicting ocean currents and a particle random walk model SEA-GEARN for oceanic dispersion of dissolved radionuclides. The system has been applied to a hypothetical accident of a nuclear submarine if it sinks in an offshore region around Japan, by using measured currents, temperature, salinity and meteorological regional objective analysis data (RANAL). Another computer code system DSOCEAN is also applied to the same hypothetical accident in order to compare the results of radionuclide dispersion in the ocean and the collective dose to the Japanese population. An equidistant-grid compartment model combined with a model of the geostrophic current analysis is used in DSOCEAN.

None

Tsujimura, Norio; Momose, Takumaro; Shinohara, Kunihiko

PNC TN8410 96-211, 37 Pages, 1996/07

PNC-TN8410-96-211.pdf:1.1MB

None

Occupational exposure in Japan From 1976 to 1992

; Kawai, Katsuo

Radiation and Society:Comprehending Radiation Risk, 2(0), p.76 - 82, 1994/10

no abstracts in English

None

Matsubara, Junko*

PNC TJ1602 91-001, 49 Pages, 1991/03

PNC-TJ1602-91-001.pdf:1.24MB

no abstracts in English

Distribution and characteristics of gamma and cosmic ray dose rate in living environment

Nagaoka, Toshi; Moriuchi, Shigeru

Hoken Butsuri, 26, p.129 - 137, 1991/00

https://doi.org/10.5453/jhps.26.129

no abstracts in English

Collective dose assessment methodology for a spent nuclear fuel reprocessing plant

Togawa, Orihiko; Homma, Toshimitsu

Proc. of the CSNI Specialist Meeting on Safety and Risk Assessment in Fuel Cycle Facilities, p.351 - 360, 1991/00

no abstracts in English