A Study of core performance for commercial FUGEN (II); Study of nuclear characteristics of 54-pin fuel assembly

*; *; *; Fukuda, Kenji*; ; *

PNC TN941 78-13VOL1, 266 Pages, 1978/01

PNC-TN941-78-13VOL1.pdf:18.12MB

Nuclear characteristics of 54-pin fuel assembly for commercial FUGEN were studied from the view points of reactor safety and fuel-cycle economy. Coolant void reactivity and power coefficient for the analysis of reactor safety, and burnup and fuel-cycle indicator for evaluating fuel-cycle cost were investigated in reference to lattice pitch, uranium and plutonium enrichment. From the present study, the following results are summarized. (1)Uranium and plutonium fuel can be used in a wide range of enrichment. (2)Natural uranium or low enriched uranium (1wt% U) fuel mixed plutonium shows the best nuclear characteristics. (3)Nuclear characteristics are improved by more introduction of plutonium in consideration of local peaking factor and power mismatch.

Study of core performance for commercial Fugen; Study of burnable poison

*; *; Fukuda, Kenji*; *; *;

PNC TN941 77-74, 34 Pages, 1977/05

PNC-TN941-77-74.pdf:0.64MB

Burnable poison in the fuel elements has been mainly used for decrease of power peak due to refueling in the Light Water Reactor. In the present study of core performance of commercial Fugen, core characteristics by introductions of Gd burnable poison was investigated from the view points of Keff, local peaking factor, mismatch factor and coolant void reactivity. The conclusions are summarized as follows. (1)Effective control or core reactivity is achieved by introduction of Gd burnable poison into a few fuel elements in inner layer. (2)Improvement of local peaking factor cannot be easily achieved by Gd burnable poison. (8)Mismatch factor is decreased from 6 % to 18 % by Gd burnable poison. (4)Coolant void reactivity shifts more negative by introduction of Gd burnable poison.

Analysis of plutonium partially loaded core; Criticality and radial cupper reaction rate distribution

*; *; *;

PNC TN941 74-37, 62 Pages, 1974/06

PNC-TN941-74-37.pdf:1.27MB

For the purpose of evaluating the accuracy of nuclear core design for plutonium loading ATR (Advanced Thermal Reactor), a series of critical experiments partially loaded with plutonium fuel assemblies has been carried out at DCA (Deuterium Critical Assembly). In this report, the analytical results on the criticallty and the radial cupper reaction rate distribution for clean core, in which no poisons such as controlrod were included, are described. The calculations were performed by making use of a cell calculation code METHUSELAH-2 and a few group diffusion code PDQ-5. METHUSELAH calculations were five energy groups, and PDQ calculations using the cell averaged group constants were two dimensions (X-Y) and three energy groups. The following conclusions were obtained from these analyses. (1)The calculated K-effective using an experimental axial buckling(B) well estimated the critical condition(K=1) of plutonium loading DCA core. (2)The accuracy of the calculated peaking factors of radial cupper reaction rates, compared with experiments, was within per cents for all cases.

Handbook of deuterium critical assembly; I. Design data of DCA core for nuclear calculation

*; *; *; *; Fukumura, Nobuo*;

PNC TN941 74-22, 52 Pages, 1974/05

PNC-TN941-74-22.pdf:1.15MB

Input data such as diameters and densities of fuel pellets which are used in nuclear calculatlon of DCA core are surmmarized in this file. The data are collected from score sheats and millsheets of DCA's reactor materials. Standared deviations from averaged values and results of chemieal analysis of the materials are also listed as a measure of accuracy of the data. Fuel materials and coolants summarized in this file are as follows;

None

*; *; *; *; Koizumi, Masumichi; ; Yumoto, Ryozo; *

PNC TN841 71-31, 431 Pages, 1971/10

PNC-TN841-71-31.pdf:23.8MB

no abstracts in English

Current status of the HIBMC, providing particle beam radiation therapy for more than 2,600 patients, and the prospects of laser-driven proton radiotherapy

Murakami, Masao*; Demizu, Yusuke*; Niwa, Yasue*; Nagayama, Shinichi*; Maeda, Takuya*; Baba, Masashi*; Miyawaki, Daisuke*; Terashima, Kazuki*; Arimura, Takeshi*; Mima, Masayuki*; et al.

no journal, ,