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JAEA Reports

Program CCOM; Coupled-channels optical model calculation with automatic parameter search

Iwamoto, Osamu

JAERI-Data/Code 2003-020, 22 Pages, 2003/12

JAERI-Data-Code-2003-020.pdf:0.98MB

A new program of coupled-channels optical model calculation has been developed for the evaluation of actinide nuclei. The code is composed of by the modules having high independency and large flexibility. The code is written by C++ language using object oriented techniques. The program has capability of fitting of the parameters even for the several nuclei at the same time. The formulae required in the calculation, details of the numerical treatments and the input parameters are described. The examples of the input file and the output are also shown.

JAEA Reports

ACUTRI: A Computer code for assessing doses to the general public due to acute tritium releases

Yokoyama, Sumi; Noguchi, Hiroshi; Ryufuku, Susumu*; Sasaki, Toshihisa*; Kurosawa, Naohiro*

JAERI-Data/Code 2002-022, 87 Pages, 2002/11

JAERI-Data-Code-2002-022.pdf:4.26MB

Tritium, which is used as a fuel of a D-T burning fusion reactor, is the most important radionuclide for the safety assessment of a nuclear fusion experimental reactor such as ITER. Thus, a computer code, ACUTRI, which calculates the radiological impact of tritium released accidentally to the atmosphere, has been developed, aiming to be of use in a discussion on licensing of a fusion experimental reactor and an environmental safety evaluation method in Japan. ACUTRI calculates an individual tritium dose based on transfer models specific to tritium in the environment. A Gaussian plume model is used for calculating the atmospheric dispersion of tritium gas (HT) and/or tritiated water (HTO). The environmental pathway model in ACUTRI considers the following internal exposures: inhalation from a primary plume (HT and/or HTO) released from the facilities and inhalation from a secondary plume (HTO) reemitted from the ground following deposition of HT and HTO. This report describes an outline of the ACUTRI code, a user guide and the results of test calculation.

JAEA Reports

Calculation of neutron flux characteristics of dalat reactor using MCNP4A code

T.V.Hung*; Sakamoto, Yukio; Yasuda, Hideshi

JAERI-Research 98-057, 25 Pages, 1998/10

JAERI-Research-98-057.pdf:1.04MB

no abstracts in English

JAEA Reports

MOSRA-Light; High speed three-dimensional nodal diffusion code for vector computers

Okumura, Keisuke

JAERI-Data/Code 98-025, 243 Pages, 1998/10

JAERI-Data-Code-98-025.pdf:10.15MB

no abstracts in English

Journal Articles

Development of burn-up calculation code system MVP-BURN based on continuous energy Monte Carlo method and its validation

Okumura, Keisuke; Nakakawa, Masayuki; Kaneko, Kunio*

Proc. of SARATOGA 1997, 1, p.495 - 508, 1997/00

no abstracts in English

Journal Articles

Virtual environment for integrated design support (VINDS) for conceptual design of a space power reactor core

*; *; *; *; Kugo, Teruhiko;

PHYSOR 96: Int. Conf. on the Physics of Reactors, 1, p.B92 - B101, 1996/00

no abstracts in English

JAEA Reports

A Computer code for calculation of radioactive nuclide generation and depletion, decay heat and $$gamma$$ ray spectrum: FPGS90

Ihara, Hitoshi; Katakura, Junichi; Nakagawa, Tsuneo

JAERI-Data/Code 95-014, 216 Pages, 1995/11

JAERI-Data-Code-95-014.pdf:6.24MB

no abstracts in English

Journal Articles

Waste characterization in decommissioning the Japan Power Demonstration Reactor by computer code systems

Sukegawa, Takenori; ; ; Yanagihara, Satoshi

The 3rd JSME/ASME Joint Int. Conf. on Nuclear Engineering (ICONE),Vol. 4, 0, p.1779 - 1784, 1995/00

no abstracts in English

JAEA Reports

A Generic safety assessment code for geologic disposal of radioactive waste; GSRW computer code users manual

Kimura, Hideo; Takahashi, Tomoyuki; ; Matsuzuru, Hideo

JAERI-M 92-161, 72 Pages, 1992/11

JAERI-M-92-161.pdf:1.91MB

no abstracts in English

Journal Articles

Parallelization of Monte Carlo shielding code MCACE and Monte Carlo criticality code KENO-IV

; Masukawa, Fumihiro; Komuro, Yuichi; Naito, Yoshitaka; *; *; *; *

Nihon Genshiryoku Gakkai-Shi, 34(6), p.533 - 543, 1992/06

 Times Cited Count:1 Percentile:17.24(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Development of a BWR core burn-up calculation code COREBN-BWR

*; Okumura, Keisuke

JAERI-M 92-068, 107 Pages, 1992/05

JAERI-M-92-068.pdf:2.79MB

no abstracts in English

JAEA Reports

UNITBURN; A Computer code for burnup calculation of a unit fuel cell

Naito, Yoshitaka; *; Masukawa, Fumihiro; *

JAERI-M 90-019, 62 Pages, 1990/02

JAERI-M-90-019.pdf:1.18MB

no abstracts in English

Journal Articles

Computer calculation for interstitial-undersized-solute complexes in an FCC metal

Takamura, Saburo; ; *; *

Journal of Physics; Condensed Matter, 1, p.4527 - 4533, 1989/00

 Times Cited Count:3 Percentile:23.72(Physics, Condensed Matter)

no abstracts in English

JAEA Reports

JAEA Reports

JAEA Reports

Journal Articles

Benchmark tests of radiation transport computer codes for reactor core and shield calculations

; *; *; *; *; *; ; *; ; ; et al.

Journal of Nuclear Science and Technology, 15(1), p.56 - 71, 1978/01

 Times Cited Count:7

no abstracts in English

Journal Articles

Biased selection of particle flight directions as a variance reduction technique in Monte Carlo calculations

;

Journal of Nuclear Science and Technology, 14(8), p.603 - 609, 1977/08

 Times Cited Count:0

no abstracts in English

22 (Records 1-20 displayed on this page)