Preparation of next generation set of group cross sections; A Task report to the Japan Nuclear Cycle Development Institute)

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JNC TJ9400 2000-005, 182 Pages, 2000/03

JNC-TJ9400-2000-005.pdf:4.74MB

The SLAROM code, performing fast reactor cell calculation based on a deterministic methodology, has been revised by adding the universal module PEACO of generating Ultra-fine group neutron spectra. The revised SLAROM, then, was utilized for evaluating reaction rate distributions in ZPPR-13A simulated by a 2-dim RZ homogeneous model, although actually ZPPR-13A composed of radial heterogereous cells. The reaction rate distributions of ZPPR-13A were also calculated by the code MVP, that is a continuous energy Monte Carlo calculation code based on a probabilistic methodology. By coparing both results, it was concluded that the module PEACO has excellent capability for evaluating highly accurate effective cross sections. Also it was proved that the use of a new fine group cross section library set (next generation set), reflecting behavior of cross sections of structural materials, such as Fe and O, in the fast neutron energy region, is indispensable for attaining a better agreement within 1% between both calculation methods. Also, for production of a next generation set of group cross sections, the code NJOY97.V107 was added to the group cross section production system and both front and end processing parts were prepared. This system was utilized to produce the new 70 group JFS-3 library using the evaluated nuclear data library JENDL-3.2. Furthermore, to confirm the capability of this new group cross section production system, the above new JFS-3 library was applied to core performance analysis of ZPPR-9 core with a 2-dim RZ homogeneous model and analysis of heterogeneous cells of ZPPR-9 core by using the deterministic method. Also the analysis using the code MVP was performed. Bycoaparison of both results the following conclusion has been derived; the deterministic method, with the PEACO module for resonance cross sections, contributes to improve accuracy of predicting reaction rate distributions and Na void reactivity in fast reactor cores. And it ...

Spallation integral experiment using lead assembly at BSF

Takada, Hiroshi

Proc. of JHF Symp. on Neutronics and Radiation Shielding for Spallation Neutron Source, p.205 - 218, 1998/00

no abstracts in English

Measurement of reaction rate distributions in a lead assembly bombarded with 500 MeV protons

Takada, Hiroshi; Meigo, Shinichiro; Sasa, Toshinobu; Tsujimoto, Kazufumi; Fukahori, Tokio; Yasuda, Hideshi

Proc. of 3rd Workshop on Simulating Accelerator Radiation Environments (SARE3), p.284 - 292, 1997/00

no abstracts in English

Development of a standard data base for FBR core nuclear design(II); JUPITER-I experlmental data book

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PNC TN9410 93-010, 502 Pages, 1992/12

PNC-TN9410-93-010.pdf:17.39MB

The present report compiles the experimental data of JUPITER phase-I, which was a joint research program between U.S.DOE and PNC of Japan, using the ZPPR facility at ANL-Idaho in 1978 to 1979. The JUPITER-I experiment was a series of critical experiments for conventional two-zone homogeneous cores of 600 to 800 MWe-class LMFBR, including seven experimental cores The nuclear characteristics recorded here include criticality, control rod reactivity, reaction rate distribution, sodium void reactivity, sample reactivity, Doppler reactivity, gamma heating and neutron spectrum. (1)ZPPR-9 : two-region cylindrical clean core with volume of app. 4,600 liters, (2)ZPPR-10A : hexagonal engineering-mockup core with 19 cotrol-rod positions(CRPs), (3)ZPPR-10B : changes seven CRPs to control rods(CRs) from ZPPR-10A, (4)ZPPR-10C : volume of app. 6,200 liters with similar core arrangement to ZPPR-10A, (5)ZPPR-10D : 31 CRPs with the same volume as ZPPR-10C, (6)ZPPR-10D/1 : changes the central CRP to a CR from ZPPR-10D, and, (7)ZPPR-10D/2 : changes seven CRPs to CRs from ZPPR-10D. 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.

In-pile Test of Tririum Release from Lithium Oxide; An Evalution Study on Neutronics and Thermohydraulics of Sweep Gas Capsule Packed with LiO Pellets

Kurasawa, T.; ; ; ; ; ; ; ; ;

JAERI-M 84-013, 47 Pages, 1984/02

JAERI-M-84-013.pdf:1.44MB

no abstracts in English

Accuracy of interpolation methods for resonance self-shielding factors

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Journal of Nuclear Science and Technology, 18(2), p.152 - 161, 1981/00

https://doi.org/10.3327/jnst.18.152

no abstracts in English

The Effect of self-shielding of the iron inelastic scattering cross section on neutron spectra

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Nuclear Science and Engineering, 77, p.250 - 256, 1981/00

https://doi.org/10.13182/NSE81-A21358

no abstracts in English