JOPSS - Search Results

JNC has been conducted a great number of irradiation tests to develop MOX fuels for Advanced Thermal Reactor and Light Water Reactors. In order to manage irradiation data consistently and to effectively utilize valuable data obtained from the irradiation tests, we commenced construction of database system on MOX fuel for water reactors in 1998 JFY. Collection and selection of irradiation data and relevant fuel fabrication data, design of the database system and preparation of assisting programs have been finished and data registration onto the system is under way according to priority at present. The database system can be operated through the menu screen on PC. About 94,000 records of data on 11 fuel assemblies in total have been registered onto the database up to the present. By conducting registration of the remaining data and some modification of the system, if necessary, the database system is expected to complete in 2000 JFY. The completed database system is to be distributed to relevant sections in JNC by means of CD-R as a media. This report is an interim report covering 1998 and 1999 JFY, which gives the structure explanation and users manual concerning to the prepared database up to the present.

Journal Articles

ROX-LWR system for almost complete burning of plutonium

Yamashita, Toshiyuki; Akie, Hiroshi; Kimura, Hideo; Takano, Hideki; Muromura, Tadasumi

IAEA-TECDOC-1122, p.309 - 320, 1999/11

no abstracts in English

JAEA Reports

Nuclear and thermal calculations on a hybrid System combining an electron accelerator and a fission reactor core

; Nomura, Masahiro;

PNC TN9410 96-205, 42 Pages, 1996/07

PNC-TN9410-96-205.pdf:1.91MB

At present, a high power CW(Continuous Wave) electron linac accelerator is under development in PNC as a part of transmutation study by accelerators. As one of applied uses, we study a hybrid reactor system combining the linac and a subcritical core with TRU fuel. This report shows nuclear and thermal calculation results to obtain characteristics of the system. In the system, an electron beam from the linac is injected into a target located in the center of the system. In the first place, the injected electrons generate photons of ray via Bremsstrahlung production. After this, these photons produce neutrons by (, n) reactions. As a result, an extinguished quantity of TRU fuel is about 0.1kg when the electron beam of incident energy 100 MeV is injected into the target over 1 year. It is proven that the system might be established from the point of thermal engineering. The hybrid reactor system can also use a proton accelerator instead of the electron one. Nuclear and thermal calculation will be performed on the system using the proton accelerator. Comparison of the extinguished quantity of TRU fuel will be performed between calculation results of both systems.

JAEA Reports

None

PNC TJ1678 95-003, 97 Pages, 1995/02

PNC-TJ1678-95-003.pdf:2.59MB

None

JAEA Reports

Optimization study of high conversion light water reactor with axially heterogeneous core

; Okumura, Keisuke; ; *; *

JAERI-M 92-030, 68 Pages, 1992/03

JAERI-M-92-030.pdf:1.66MB

no abstracts in English

JAEA Reports

Studies of neutronics calculation of high conversion light water reactor

; Okumura, Keisuke; Takano, Hideki;

JAERI-M 90-109, 49 Pages, 1990/07

JAERI-M-90-109.pdf:1.4MB

no abstracts in English

Journal Articles

Sensitivity analysis of cell neutronic parameters in high-conversion light-water reactors

*; *;

Journal of Nuclear Science and Technology, 24(8), p.610 - 620, 1987/08

https://doi.org/10.3327/jnst.24.610

Times Cited Count：4 Percentile：44.92(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Effect of transplutonium nuclides on burnup reactivity changes in HCLWRs

;

Journal of Nuclear Science and Technology, 24(6), p.501 - 502, 1987/06

https://doi.org/10.3327/jnst.24.501

Times Cited Count：3 Percentile：51.95(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Preliminary Analysis of Nuclear Characteristics Experiments in Fast Reactors for Alternative Structural Materials

;

JAERI-M 83-188, 61 Pages, 1983/11

JAERI-M-83-188.pdf:1.5MB

no abstracts in English

JAEA Reports

Sodium spray fire analysis (II)

; *

PNC TN241 83-10, 229 Pages, 1983/07

PNC-TN241-83-10.pdf:13.91MB

Sodium spray fire experiments using a 21 m $^{3}$ vessel were Performed in order to validate the computer code SPRAY-III. The results of precalculations has been reported in a preceding report, Sodium Spray Fire Analysis. In this study, the validation of SPRAY-III was conducted using the experimental results and the accuracy of calculated results was discussed. The following results were obtained: (1)study under inert gas atmosphere. (a)The peak pressure and temperature obtained by the analysis overestimate the experimental results. But the calculated pressure rose monotonically till the termination of spray injection and it was different from the experimental peak which appeared during the injection. The rise rates of pressure and temperature in analyses were lower than those in experiments. (b)The calculated temperatures of the steel wall liner were only about 55 to 75 % of the experimental values at the end of sodium injection. But the comparison between analysis and experiment with regard to the temperature of mortar wall showed a fairly good agreement. (c)The averaged pool temperature at the end of sodium injection was found to be slightly lower in analysis than in experiment. The analysis shows that the heat transfer between the pool and the gases hardly affects the results during sodium injection. (2)Study under air atmosphere. (a)When all reaction products were assumed to be peroxide in the same manner as in the safety analysis of Monju, the increase rates of both the pressure and the temperature as well as their peak values were found to be underestimation. Hence to obtain conservative results in this 21 m $^{3}$ vessel, an increase in the rate constant of reaction with oxygen (Vo from 300 to 1000 ft/sec) must be assumed. However, this value should be investigated in the near future for application to the safety analysis of Monju. (b)The comparison between analysis and experiment with regard to the temperature of the mortar showed a fairly good agreement. ..