JOPSS - Search Results

JAEA Reports

None

Fujita, Reiko*; *; Kondo, Naruhito*; Utsunomiya, Kazuhiro*

JNC TJ8420 2000-004, 41 Pages, 2000/03

JNC-TJ8420-2000-004.pdf:5.08MB

no abstracts in English

JAEA Reports

Thermal calculation of bituminized product, 1; Thermal evaluation of bituminized product using heat transporting calculation

Miura, Akihiko;

JNC TN8410 99-044, 189 Pages, 1999/10

JNC-TN8410-99-044.pdf:7.18MB

This report includes several results that were made by calculation with several methods to clarify the cause of the fire and explosion incident. In the early times, we didn't have exact information of chemicaI property, reaction rate and any physical constants that we needed. But because the only data that indicate the cooling process of bituminized product was reported, we made heat-transporting calculation with taking this data. Based on the theory of the thermal hazard evaluation that was called Semenov theory or Frank-Kamenetskii theory, the amount of heat generation was estimated using the heat transporting calculation. Common theories were introduced in first section. In the second section, several results of heat transporting calculation were indicated. Calculations were made as follows. First, the model of bituminized product that was filled in the drum was created with the data of cooling process. Second, when the heat was generated in the drum, time-dependent temperature distribution was calculated. And last, judging from the balance of heat generation and heat radiation the critical heat rate was estimated.

JAEA Reports

None

; ; ; ; ; ;

PNC TN8440 98-025, 111 Pages, 1998/07

PNC-TN8440-98-025.pdf:11.06MB

None

Journal Articles

Application of a Phoswich detector for simultaneous counting of - and ()-rays in a rotating drum-cell type monitor

Usuda, Shigekazu; Yasuda, Kenichiro; Sakurai, Satoshi; Takahashi, Toshiyuki; Gunji, Hideho*; P.Howarth*

INMM 39th Annual Meeting Proceedings (CD-ROM), 27, 6 Pages, 1998/00

no abstracts in English

Journal Articles

Improvement of a rotating drum-cell type alpha monitor and its performance test

Usuda, Shigekazu; Yasuda, Kenichiro; Sakurai, Satoshi; Takahashi, Toshiyuki; Gunji, Hideho*

Dai-18-Kai Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Nenji Taikai Hobunshu, p.142 - 148, 1997/11

no abstracts in English

Journal Articles

Vulcanization of natural rubber latex with low energy electron accelerator

Makuuchi, Keizo; Yoshii, Fumio; *; *; F.Akhtar*

Nihon Gomu Kyokai-Shi, 69(7), p.500 - 506, 1996/00

https://doi.org/10.2324/gomu.69.500

no abstracts in English

JAEA Reports

Natural circulation flow analysis of middle size ATR

*; *

PNC TJ9381 94-001, 84 Pages, 1994/02

PNC-TJ9381-94-001.pdf:1.6MB

The study in last year examined the realization of 1000MWt natural circulation ATR. In this study. The sensitivity analysis is did making for the design. The results are as below. (1)The influence of riser pipe diameter. The natural circulation on riser pipe 3B is analyzed. 3B pipe is cheaper than 5B riser pipe that is a base condition. The results are that fuel dryout is happen by 1.8MW channel power on 3B, but is not happen on 5B riser pipe. (2)The influence of the riser pipe number reduction and the riser pipe diameter change. The case of connection 2 pressure tubes by Y piece pipe is analyzed. In this case, the riser pipe number is half. The cases that riser pipe is 5B and 4B are analyzed. The results are as below. (a)Natural circulation flow lower by riser pipe number is half. (b)Fuel dryout is happen by 1.8MW channel power on 4B, but is not happen on 5B. (3)The influence of the middle position header connection and the riser pipe diameter change, The case of connection 50 pressure tubes by the middle position header is analysed. The cases that riser pipe is 24B and 32B are analyzed. The results are as below. (a)In 2 cases, natural circulation flow lower as compared with base case. (b)In 2 cases, fuel dryout are not happen by 1.8MW channel power. (4)The influence of pressure tube diameter. The case of pressure tube diameter widening is analyzed. So, the pressure loss of pressure tube domain govern the flow. (a)Natural circulation flow increase by pressure tube diameter widening. (b)The flow swing is by pressure tube diameter widening. (c)In analysis cases, fuel dryout is not happen. We get 1.8MW channel power on the condition that riser pipe is 4B, riser pipe is connected by Y piece pipe, pressure tube diameter is 122.0mm.

JAEA Reports

None

PNC TN1410 92-006, 17 Pages, 1991/12

PNC-TN1410-92-006.pdf:0.86MB

no abstracts in English

JAEA Reports

None

; Koakutsu, Masayuki; *; Yoshida, Michihiro; ; *;

PNC TN8450 91-006, 77 Pages, 1991/03

PNC-TN8450-91-006.pdf:2.09MB

None

JAEA Reports

None

; Koakutsu, Masayuki; *; Yoshida, Michihiro; ; *;

PNC TN8450 91-005, 103 Pages, 1991/02

PNC-TN8450-91-005.pdf:2.7MB

None

Journal Articles

Low level combustible waste management system of JAERI-OARAI

; ; Abe, Masayoshi

Hoken Butsuri, 26, p.47 - 58, 1991/00

https://doi.org/10.5453/jhps.26.47

no abstracts in English

JAEA Reports

Outline of air-cooling thermal transient test facility

*; *; Uno, Tetsuro*

PNC TN9410 86-029, 68 Pages, 1986/02

PNC-TN9410-86-029.pdf:12.61MB

A new test facility "Air-Cooling Thermal Transient Test Facility" (ATTF) was constructed at O-arai Engineering Center. This test facility is utilized, in the first place, for evaluating the strength of outlet tube-sheets of steam generators of FBR Plants. The objectives of the tube-sheet model tests are as follows. The first is to investigate and evaluate the strain concentration in the plastic region. The second is to confirm the adequacy of the design criteria for the prototype reactor MONJU. The third is to confirm the safety margin for failure incorporated in the design evaluation methods. ATTF can impose severe thermal loadings (only cold shock) on the test specimens. The facility produces compressed air (Max. 35kg/cm $^{2}$ G) by two large-sized compressors, and stores it in a storage tank (about 60m $^{3}$ ). After a test specimen is heated up to the aimed temperature the compressed air passes through the test specimens quickly by opening the valve to apply cold shock and is released in the atmosphere. Each main loop pipe is 8 inches in diameter and the flow rate is max. 10kg/s in compressed air. The most severe down thermal transient condition is from 550 $^{circ}$ C to 150 $^{circ}$ C (for tube-sheet model) in about 4 min. The test section can be modified for various kinds of structures, which should be air-tight and have the maximum pressure of 8kg/cm $^{2}$ G. The facility is operated automatically by two sequencer controllers. One of the main features of ATTF is the adoption of compressed air instead of sodium as coolant. By using compressed air, various kinds of sensors which can not be used in the sodium environment can be used in ATTF; particularly strain gages can be used effectively to obtain strain distribution for thermal transient condition, and the location as well as the mode of failure of test specimens can be recognized easily through the detection of crack initiation and the observation of crack growth. ATTF is expected to be a powerful ...

JAEA Reports

Long-term thermo-hydraulic analysis in large-scale sodium-water reaction (Analysis of SWAT-3 Runs 4, 5, 6 and 7 by SWAC-13E); Large-scale sodium-water reaction analysis (Report No.14)

*; *; Kuroha, Mitsuo; *; *; *; *

PNC TN941 85-53, 144 Pages, 1985/03

PNC-TN941-85-53.pdf:3.01MB

SWAC13E is a one-dimensional thermo-hydraulic computer program to analyze large scale sodium-water reaction accidents in an LMFBR steam generator. The code is the advanced version of SWAC13, the long-term hydraulic analysis module of SWACS; the energy conservation is taken into consideration in the new version to add the function to analyze the temperature behavior of the reaction. The present document covers the validation study of the code by using the large leak data of the Steam Generator Safety Test Facility (SWAT-3). The analytical parameters are as follows: (1)Model of relative velocity. (2)Void/droplet density. (3)The number of nodes where water leaks. (4)Reaction heat. It is concluded that the code can analyze the phenomena with a reasonable conservatism by choosing the proper value of the parameters.

JAEA Reports