Refine your search:     
Report No.
 - 
Search Results: Records 1-5 displayed on this page of 5
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

JAEA Reports

Measurement of fast neutron induced fission cross section of minor-actinide

*

PNC-TJ9601 98-002, 115 Pages, 1998/03

PNC-TJ9601-98-002.pdf:2.57MB

In fuel cycles with recycled actinide, core characteristics are largely influenced by minor actinide (MA: Np, Am), Accurate nuclear data of MA such as fission cross section are required to estimate the effect of MA with high accuracy. In this study, fast neutron induced fission cross section of MA was measured using Dynamitron Accelerator in Tohoku University. New or improved techniques and tools with high precision and fast timing capability were developed for this study. Those are as follows: (1)Development of a sealed fission chamber,(2)Intensification of Li neutron target, (3)Improvement of time-resolution of Time-of-Right (TOF) electronic circuit, (4)Introduction of MA (Np237, Am241 and Am243) samples with large sample mass and (5)Introduction of a U235 sample with high purity. Using these improved tools and samples, fission cross section of Np237 was measured between 10 to 100 keV. On the other hand, averaged fission cross section for Maxwell distribution spectrum with kt=25.3 keV was measured for Am241 and Am243.

JAEA Reports

Measurement of nuclear data for minor actinides with lead slowing-down spectrometer - III

*

PNC-TJ9604 97-001, 108 Pages, 1997/03

PNC-TJ9604-97-001.pdf:4.05MB

A lead slowing-down spectrometer was installed coupled to the 46 MeV electron linac at Research Reactor Institute, Kyoto university (KURRI). Characteristics of the Kyoto University Lead Slowing-down Spectrometer (KULS) were measured for (1)the relation between neutron slowing-down time t($$mu$$s) and energy E (keV) (E=190/t$$^{2}$$ in Bi hole and E=156/$$^{2}$$ in Pb hole), (2)energy resolutlon ($$sim$$40 % in Bi and Pb holes), and (3)neutron energy spectrum by the neutron TOF method. The results obtained by the MCNP code were in general agreement with these experimental ones. The KULS has been applied to the fission cross section measurements of Am-241, Am-243 and Am-242m relative to that of U-235 from $$sim$$0.1 eV to $$sim$$10 keV, making use of the back-to-back type double fission chambers. For Am-241, Dabbs and ENDF/B-VI data are in good agreement with the present measurement. The JEND L-3.2 data are smaller by a factor of 2 between 10 and 200 eV. The ENDF/B-VI data for Am-243 are lower between 15 and 60 eV, and the JENDL-3.2 are lower in general above 100 eV. It has been found that the preliminary result for the Am-242m(n,f) reaction is close to the ENDF/B-VI and the JENDL-3.2 data. Thermal neutron cross sections for Am-241 and Am-243 have also been measured in a standard Maxwellian distribution spectrum field. Finally, aiming at the measurement of capture cross section for MA nuclides, the experimental investigation for Np-237 sample ($$sim$$2 mg) has been performed with the KULS. Due to the comparable background counts to the foreground ones, the capture events from the sample have scarecely been detected with an Ar-gas proportional counter.

JAEA Reports

Measurement of fast neutron induced fission cross section of minor-actinide

*

PNC-TJ9601 97-001, 51 Pages, 1997/03

PNC-TJ9601-97-001.pdf:1.05MB

In fuel cycles with recycled actinide, core characteristics are largely influenced by minor actinide (MA:Np, Am, Cm). Accurate nuclear data of MA such as fission cross section are required to estimate the effect of MA with high accuracy.In this study fast neutron induced fission cross section of MA is measured using Dynamitron Accelerator in Tohoku University. The experimental method and the samples, which were developed or introduced during the last year, were improved in this fiscal year: (1)Development of a sealed fission chamber, (2)Intensification of Li neutron target, (3)Improvement of time-resolution of Time-of-flight (TOF) electronic circuit, (4)Introduction of Np237 samples with large sample mass and (5)Introduction of a U235 sample with high purity. Using these improved tools and samples, the fission cross section ratio of NP237 relative to U235 was measured between 5 to 100keV, and the fission cross section of Np237 was deduced. On the other hand, samples of Am241 and Am243 were obtained from Japan Atomic Energy Research Institute (JAERI) after investigating fission cross section of two americium isotopes (Am241 and Am243) which are important for core physics calculation of fast reactors.

JAEA Reports

None

PNC-TJ1545 95-001, 150 Pages, 1995/03

PNC-TJ1545-95-001.pdf:5.28MB

no abstracts in English

JAEA Reports

None

PNC-TJ1214 91-010, 119 Pages, 1991/10

PNC-TJ1214-91-010.pdf:2.1MB

None

5 (Records 1-5 displayed on this page)
  • 1