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Journal Articles

Nuclear data in radiation protection dosimetry

Satoh, Daiki

JAEA-Conf 2012-001, p.27 - 31, 2012/07

In a field of radiation protection dosimetry, nuclear data have been utilized for calculations of fluence, dose, and heat against mediums such as human body tissues, shielding walls, and the environment. Thanks to the use of nuclear data, the accuracy of those calculations is improved significantly. The good relationship between the nuclear data and dosimetry calculations will be introduced in this presentation. In addition, some requests for a nuclear data community are also shown to solve the problems in the use of nuclear data for radiation protection dosimetry.

Journal Articles

Development of the ORIGEN2 library for light water reactors based on JENDL-4.0

Okumura, Keisuke; Kojima, Kensuke; Okamoto, Tsutomu

JAEA-Conf 2012-001, p.89 - 94, 2012/07

New ORIGEN2 libraries (ORLIBJ40) for light water reactors were developed based on JENDL-4.0. It was validated by post irradiation examination analyses of nuclear spent fuels. As a result, it was found that drastic improvements were achieved especially for the inventory estimations of minor actinides (Np, Am and Cm isotopes) and fission products sensitive to cross sections (Eu and Sm isotopes) compared with old ORIGEN2 libraries. Furthermore, radioactivity of long-lived fission products, such as $$^{79}$$Se and $$^{135}$$Cs were also improved because of implementations of new half-life data. These nuclides are very important for long-term safety assessment of a geological disposal of the vitrified wastes.

Journal Articles

Nuclear data for prediction of isotope generation and depletion

Okumura, Keisuke

JAEA-Conf 2012-001, p.39 - 44, 2012/07

First, calculation schemes of nuclide generation and depletion are briefly shown by taking up three different burn-up calculation codes, MVP-BURN, MOSRA-SRAC and ORIGEN2. Then, as examples of validation of burn-up calculations with these codes and JENDL-4.0, we show results of post irradiation examination analyses for LWR spent fuel compositions. At last, recent progress is introduced on inventory prediction of $$^{79}$$Se in LWR spent fuels, which is very important for long-term safety assessment of a geological disposal of the vitrified wastes.

Journal Articles

Neutron capture cross section of palladium-107 in the thermal-neutron energy region

Nakamura, Shoji; Ota, Masayuki; Oshima, Masumi; Kitatani, Fumito; Kimura, Atsushi; Kin, Tadahiro; Koizumi, Mitsuo; Goko, Shinji*; Toh, Yosuke; Hara, Kaoru; et al.

JAEA-Conf 2012-001, p.147 - 152, 2012/07

Journal Articles

Fast Breeder Reactor core design study using JENDL-4.0

Ohgama, Kazuya; Oki, Shigeo; Okubo, Tsutomu

JAEA-Conf 2012-001, p.21 - 26, 2012/07

Oral presentation

Severe accident analysis and related nuclear data

Tsujimoto, Kazufumi

no journal, , 

The design of any nuclear power plant is impossible without safety evaluation. Analysis of design basis accident (DBA) considered to prove safety features of installed equipment to prevent accidents. On the other hand, analysis of severe accidents plays a very important role in risk assessments in order to reduce the probability of severe accidents with core melt to the level of 10$$^{-6}$$ and less. In comparison to DBA, the main differences for the modeling of severe accident are connected fact that the object of modeling itself is not well defined due to changes of geometrical factors, composition of the melt and its properties. Evaluations related to nuclear data in the analysis of severe accidents are as following; (1) core composition and source term, (2) decay heat, and (3) criticality.

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