ISSN:0022-3131    

DOI:10.1080/18811248.1989.9734260

出版商:Taylor & Francis Group    

年代:1989

数据来源: Taylor

ISSN:0022-3131    

DOI:10.1080/18811248.1989.9734261

出版商:Taylor & Francis Group    

年代:1989

数据来源: Taylor

摘要:

Three versions of Japanese Evaluated Nuclear Data Library (JENDL) are briefly explained. The first version, JENDL-1, was made aiming mainly at application to fast reactors. The second version, JENDL-2, was built as a bigger general purpose evaluated nuclear data library. It stores nuclear data for 181 nuclides. It has, however, some drawbacks particularly for fusion neutronics calculation. To remove these drawbacks of JENDL-2 and further extend its applicability, the third version, JENDL-3, has now been made. JENDL-3 includes photon-production data for some nuclides, in addition to the data contained in JENDL-2.

ISSN:0022-3131    

DOI:10.1080/18811248.1989.9734262

出版商:Taylor & Francis Group    

年代:1989

数据来源: Taylor

摘要:

Neutron induced fission cross sections relative to235U have been measured for ten actinide nuclides:232Th,233U,234U,236U,238U,237Np,239Pu,240Pu,242Pu and243Am. The energy ranges measured are 0.5–7 MeV and around 14 MeV except for a few cases. A back to back fission chamber with 10–170/μg/cm2thick sample foil is used. The methods of the determination of number of atoms and the fission rate measurement, the corrections applied in obtaining the cross section ratio are briefly described. The results are compared with JENDL-2.

ISSN:0022-3131    

DOI:10.1080/18811248.1989.9734263

出版商:Taylor & Francis Group    

年代:1989

数据来源: Taylor

摘要:

This is a brief review of the measurements of double differential neutron emission cross sections, which have been done at the OKTAVIAN facility of Osaka University since 1981, for many elements of fusion reactor materials. In the phase-1 experiments, double differential cross sections with high energy resolution and good counting satisfies were accumulated for D, Li, Be, B, C, N, O, F, Na, Al, Si, CI, Ti, Cr, Mn, Fe, Ni, Cu, Zr, Nb, Mo, W and Pb. The ring geometry TOF spectrometer was used in the phase-1, a drawback of which was due to the considerable variation of incident energy. In the phase-2 experiments, a new TOF spectrometer was installed for fixing the incident neutron energy to be 14.1 MeV and keeping the energy resolution and counting statistics. We can then obtain angle-integrated emission spectra and partial differential cross sections from measured double differential neutron emission cross sections. In the phase-2, measurements have been done for Be, C,10B,11B, F, Mg, Al, Si, V, Cr, Fe, Ni, Cu, Pb and Bi. All the data in the two phases have been efficiently utilized to improve evaluated neutron cross sections in JENDL-3, EFF-l and ENDF/B-VI.

ISSN:0022-3131    

DOI:10.1080/18811248.1989.9734264

出版商:Taylor & Francis Group    

年代:1989

数据来源: Taylor

摘要:

The JAERI thermal reactor standard neutronics design code system, SRAC has been developed at JAERI to establish an overall neutronics calculation code system. While incorporating the conventional transport and diffusion codes, SRAC is characterized by application of the collision probability method on the resonance absorption and the cell calculations over the whole neutron energy. A comprehensive set of collision probability routines for 13 types of geometries yields wide application of SRAC to almost all types of thermal reactors. Since the functions have been qualified through a wide range of benchmark calculations, SRAC has been used for neutronics design of the core conversion of JAERI research and test reactors and the analyses of critica! experiments performed at JAERI and domestic universities. Recent modifications of methods and data extend its applicability to HCLWRs cores.

ISSN:0022-3131    

DOI:10.1080/18811248.1989.9734265

出版商:Taylor & Francis Group    

年代:1989

数据来源: Taylor

摘要:

A variety of discrete ordinates codes have been developed during the past ten years for radiation shielding calculations in rather complicated geometries and also for transport calculations of Bremsstrahlung photons.

ISSN:0022-3131    

DOI:10.1080/18811248.1989.9734266

出版商:Taylor & Francis Group    

年代:1989

数据来源: Taylor

摘要:

Continuous efforts have been made to perform basic and feasibility studies for the design of high conversion light water reactors (HCLWRs) at Japan Atomic Energy Research Institute (JAERI), several universities, PWR and BWR fabricators and utilities. The design efforts have aimed at achieving both high conversion and high burnup. This paper reviews the recent activities related to the development of HCLWRs in Japan.

ISSN:0022-3131    

DOI:10.1080/18811248.1989.9734267

出版商:Taylor & Francis Group    

年代:1989

数据来源: Taylor

摘要:

A review is presented on the recent research activities in Japan in the field of reactor noise analysis. It covers six selected areas : nonlinear stochastic theory and identification of nonlinearity in nuclear reactor dynamics, structural identificationviareactor noise analysis, autoregressive model and contraction of information, knowledge-based support system for reactor noise analysis and diagnosis, reactor noise analysis benchmark tests and application of noise analysis to BWR plant diagnosis.

ISSN:0022-3131    

DOI:10.1080/18811248.1989.9734268

出版商:Taylor & Francis Group    

年代:1989

数据来源: Taylor

摘要:

This paper reviews contributions in the application of knowledge information technology to nuclear power plants with emphasis on case descriptions of knowledge-based system development in three major application domains; design and planning, operation and maintenance, and man- machine interface. Knowledge-based systems referred to are a plant layout CAD system, a maintenance work scheduling system, and a man-machine interface system.

ISSN:0022-3131    

DOI:10.1080/18811248.1989.9734269

出版商:Taylor & Francis Group    

年代:1989

数据来源: Taylor