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Journal Articles

Research and development activities for accelerator driven system at JAERI

Tsujimoto, Kazufumi; Sasa, Toshinobu; Nishihara, Kenji; Oigawa, Hiroyuki; Takano, Hideki*

Proceedings of International Conference on Physics of Fuel Cycles and Advanced Nuclear Systems; Global Developments (PHYSOR 2004) (CD-ROM), 8 Pages, 2004/04

The Japan Atomic Energy Research Institute (JAERI) is developing an Accelerator Driven System (ADS) for transmutation of nuclear waste such as minor actinide (MA) and long-lived fission product (LLFP). To study and evaluate the feasibility of ADS by physical and engineering viewpoints, the Transmutation Experimental Facility (TEF) is proposed under a framework of J-PARC (Japan Proton Accelerator Research Complex) project. The TEF consists of two facilities named as Transmutation Physics Experimental Facility (TEF-P) and ADS Target Test Facility (TEF-T). The TEF-P consists of a zero-power critical assembly which is operated with a low power proton beam to research the reactor physics and the controllability of ADS. The TEF-T is a facility for material irradiation and partial mockup of beam window which can accept a maximum 600MeV-200kW proton beam into the Pb-Bi eutectic target. The purposes, experimental items and the specifications of the facilities are described.

JAEA Reports

None

; Numata, Kazuyuki*; ; *; Oigawa, Hiroyuki*

JNC-TY9400 2000-006, 162 Pages, 2000/04

JNC-TY9400-2000-006.pdf:4.57MB

no abstracts in English

Journal Articles

Improvement of neutron source introduction method for absolute measurements of low reactor power

Yamamoto, Toshihiro; Miyoshi, Yoshinori

Journal of Nuclear Science and Technology, 36(11), p.1069 - 1075, 1999/11

 Times Cited Count:2 Percentile:76.48(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Analysis of measurements for a Uranium-free core experiment at the BFS-2 critical assembly

Hunter

JNC-TN9400 99-049, 74 Pages, 1999/04

JNC-TN9400-99-049.pdf:2.03MB

This document describes a series of calculations that were carried out to model various measurements from the BFS-58-1-I1 experiment. BFS-58-1-I1 was a mock-up of a uranium-free, Pu burning core at BFS-2, a Russian critical assembly operated by IPPE. The experiment measured values of keff, Na void reactivity worth, material sample reactivity worths and reaction rate ratios. The experiments were modelled using a number of different methods. Basic nuclear data was taken from JENDL-3.2, in either 70 or 18 groups. Cross-section data for the various material regions of the assembly were calculated by either SLAROM or CASUP; the heterogeneous structure of the core regions was modelled in these calculations, with 3 different options considered for representing the (essentially 2d) geometry of the assembly components in a 1D cell model. Whole reactor calculations of flux and keff were done using both a diffusion model (CITATION) and a transport model (TWOTRAN2), both using an RZ geometry. Reactivity worths were calculated both directly from differences in keff values and by using the exact perturbation calculations of PERKY and SN-PERT (for CITATION and TWOTRAN2, respectively). Initial calculations included a number of inaccuracies in the assembly representation, a result of communication difficulties between JNC and IPPE; these errors were removed for the final calculations that are presented. Calculations for the experiments have also been carried out in Russia (IPPE) and France (CEA) as part of an international comparison exercise, some of those results are also presented here. The calculated value of keff was 1.1%$$delta$$k/k higher than the measured value, Na void worth C/E values were $$sim$$1.06; these results were considered to be reasonable. (Discrepancies in certain Na void values were probably due to experimental causes, though the efect should be investigated in any future experiments.) several sample worth values were small compared with calculational uncertaint

Journal Articles

JAEA Reports

Educational reactor-physics experiments with the critical assembly TCA

*; *; *; Horiki, Oichiro*; Suzaki, Takenori

JAERI-Review 97-014, 43 Pages, 1997/10

JAERI-Review-97-014.pdf:1.2MB

no abstracts in English

JAEA Reports

Development of a standard data base for FBR core nuclear design (VI): JUPITER-II experimental data book

*

PNC-TN9450 96-052, 694 Pages, 1996/10

PNC-TN9450-96-052.pdf:45.48MB

The present report compiles the experimental data of JUPITER Phase-II, which was a joint research program between U.S. DOE and PNC of Japan, using the ZPPR facility, which stands for Zero Power Physics Reactor at ANL-Idaho in l982 to l984. The JUPITER-II experiment was a series of critical experiments for conventional radial heterogeneous cores of 650 MWe class LMFBR, including six experimental cores. The nuclear characteristics recorded here include criticality, control rod reactivity, reaction rate distribution, sodium void reactivity, sample reactivity, Doppler reactivity and gamma heating. The present work is a part of efforts to develop a standard data base for LMFBR core nuclear design at PNC. The detail of experimental data is thoroughly recorded here so as to re-analyze these experiments in future. In addition, these experimental data are installed in the computer system at OEC for convenience of analytical code input.

Journal Articles

New facilities for criticality safety experiments; STACY and TRACY in NUCEF

Tsujino, Takeshi; Takeshita, Isao; ; Nomura, Masayuki; *

Proc. of the 8th Pacific Basin Nuclear Conf., p.9-E-1 - 9-E-6, 1992/00

no abstracts in English

JAEA Reports

None

*

PNC-TN1420 91-001, 258 Pages, 1990/11

PNC-TN1420-91-001.pdf:9.24MB

no abstracts in English

JAEA Reports

None

Takeda, Toshikazu*; *; *

PNC-TJ2605 87-001, 204 Pages, 1987/03

PNC-TJ2605-87-001.pdf:3.82MB

no abstracts in English

JAEA Reports

None

*; *; *

PNC-TJ2500 86-002, 126 Pages, 1986/03

PNC-TJ2500-86-002.pdf:3.76MB

no abstracts in English

Journal Articles

Measurements of reactivity effects caused by surface waves excited in nuclear fuel systems having a free surface

; Miyoshi, Yoshinori

Journal of Nuclear Science and Technology, 23(9), p.840 - 842, 1986/00

 Times Cited Count:2 Percentile:55.28(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

None

PNC-TJ265 83-01, 144 Pages, 1983/03

PNC-TJ265-83-01.pdf:2.67MB

no abstracts in English

JAEA Reports

None

PNC-TJ265 82-01, 73 Pages, 1982/03

PNC-TJ265-82-01.pdf:1.72MB

no abstracts in English

JAEA Reports

JAEA Reports

JAERI fast reactor group constants set, Version II

; ; Nakagawa, Masayuki; ; Katsuragi, Satoru

JAERI 1255, 200 Pages, 1978/03

JAERI-1255.pdf:12.07MB

no abstracts in English

JAEA Reports

JAEA Reports

None

; ; ; Murano, Toru*; Wakabayashi, Hiroaki*; Yoshii, Koji*

PNC-TN841 77-06, 76 Pages, 1976/03

PNC-TN841-77-06.pdf:4.64MB

no abstracts in English

JAEA Reports

27 (Records 1-20 displayed on this page)