JPRS ID: 9904 WORLDWIDE REPORT NUCLEAR DEVELOPMENT AND PROLIFERATION
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JPRS L/9904
11 August 1981
Worldwide Re ort
p
NUCLEAR DEVELOPMENT AND PROLIFERATION
CFOUO 9/81)
,
.
FB~$ FORE~GN BROADCAST INFORMATION SERVICE
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JPRS L/9904
11 August 1981
WORLDW I DE REPORT
NUCLEAR DEVELOPMENT AND PROLIFERATION
�""TO 9/81)
~ r vv
CONTENTS
ASIA
JAPAN
Development of trradiation Chamber for Fusion Reactor
(TECHNOCRAT, May 81) 1
Slab Core Reflood Test Facility Produced
(TECHPlOCRAT, May 81) 3
Briefs
High Purity Plasma 5
Hydrogen Plasma Laser Oscillation 5
Reactor Vessel Cover Improvement 5
Giant Electron Lineac 6
Radiation-Resistant XMA b
NEAR EAST AND NORTH AFRICA
INTER-ARAB AFFAIRS
Nuclear Option Discussed in Face of Israeli Raid
(AL-WATAN AL-'ARABI, 2 Jul 81) 7
WEST EUROPE
FEDERAL REPUBLIC OF GERMANY
FRG Scientists Aid Pakistan Nuclear Development
(Karl Guenther Barth; STERN, 2 Jul 81) 10
- a - [ITI - WW - 141 FOUOJ
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JAPAN
DEVELOPMENT OF IRRADIAT CON CHAMBER FOR FUSION REAC`i:1R
Tokyo TECHNOCRAT in English Vol 14, No 5, May 81 p 59
[Text] In an effort to develop exotic materials needed for nuclear fusion reac-
tors, the National Research Institute for Metals of the Science and Technology
Agency plans to build an irradiation creep simulation test facility, and has de-
cided to develop an irradiation chamber called a target test component starting
in FY 1981. To produce fusion reactors, irrad~iation test data that will play a
key role in core structure design and r.ew materials development are urgently
needed. Consequently, with construction planned for fiscal 1982-1984, the in-
stitute will build at its laboratory in Tsukuba Research Garden City (provisional
name), a"light ion irradiation creep test facility," a new type of cyclotron that
will irradiate protons and carry out creep or fatigue tests ~r materials.
The Japan Atomic Energy Research Institute is proposing to use SUS31b stainless
steel for the experimental fusion reactor in its design. Since there are almost
no d~ta available for irradiation by neutrons of 14 mega electron volts (MeV), a
lower reactor output must be specified to avoid higher irradiation damage. Stain-
less steel SUS316 could not survive the operating conditions of the next-stage
prototype reactor, necessitating new materiat development. Above all, neutron
energy in fusion reactors is 14MeV in contrast to about 1MeV in fast breeder re-
actors, in addition to far more helium being generated that can cause protlems
for fusion core materials.
To meet irradiation test requirements for the more severe conditions of fusion
reactors than those in FBRs, the institute plans to introduce a simulation test-
- ing technique to collect irradiation test data for core structure designing and
new materia]. development.
According to the ~lan, a compact cyclotron capable of accelerating protons and
alpha rays up to 16MeV is expected to be built in FY 1982-1984. First in fiscal
1981, costing ~27 million, a demonstration irradiation chamber will be developed
to conduct creep and fatigue tests, in order to acquire reliable information for
the irradiation creep simulation test facility system that will be built for
approx. ~500 million. The new type cyclotron features material endurance tests
that can be carried out under simulated conditions. Furthermore, the tesCing
facility is capable of helium irradiation followed by proton bombardment to
evaluate both irradiation esnbrittlement and creep simultaneously.
1
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The device will provide a maximum energy of 16MeV for protons and alpha rays,
which corresponds to the ability of the protons to penetrate, or helium ions
to halr. in, O.lmm thick stainless steel (SUS316). The proposed test tempera--
tures for the equipment are 300-10U0�C, with a maximum test stress of 50kg per
square mm.
Counter balance
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Infrared ray
thermometer ~ t
Window �
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Loads ~
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Fig. l. target Test Section of Irradiatio~
Cceep l'est Facility
COPYRIGHT: 1981 Fuji Marketing Research Co., Ltd.
CSO: 5100/4540
2
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JAPAN
SLAB CORE REFLOOD TEST FACILITY PRODliCED
Tokyo TECHNOCRAT in English Vol 14, No 5, May 81 p 59
[Text] Ishikawajima-Harima Heavy Industries Co. has produced a slab core re-
flood test facility (SCTF). It completed a large-scale cylindrical core reflood
test facility in 1979. These systems can simulate reflood phenomena in pressur-
ized water reactors, the process that during a loss-of-coolant accident, an emer-
gency core cooling system is activated to reflood exposed and overheated core
fuels to prevent assembly failure.
SCTF will perform a two-dimensional study on core reflooding. It is roughly
rectangular in shape, compared with the cylindrical shape of the cylindrical
core test facility. This is the same as the operating reactors.
The test chamber in the facility is a flat, standing type pressure vessel with
a body formed by plates. The vessel consists of three sections: lower, middle,
and upper b~dies. Ea~h is connected with oval flanges, and the top and bottom
are sealed with oval blank flanges. Inside, a partitioning board fortns a down-
comer section, and the external surface is ribbed to give added strength to the
' plates. Nozzles to attach measuring instruments are also located on the exterior
surface.
The main specifications are as fol~ows:
- Design pressure: 6 kg f/cm2
Design temperature: 350�C
Dimension:
Ma~or axis (interior width): 3541 mm
Manor axis (interior width): 460 mm
Thickness: 105m~
Height: 8911mm
Materials:
Flat parts: (SGV49) + (SUS304) clad
Round parts: (SF50) + (SUS304) clad
Moreover, mock-up fuel assemblies lined up side by side in the test chamber con-
sist of 8 bundles each providing dummy fuel rods in a 16 x 16 configuration to
form a siniulated reactor core. The core, to avoid flow interference by the core
wall while reflooding, the interior is covered with a honeycomb slab that is
supported and shielded by a barrel structure.
3
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