GB1137939A

GB1137939A – A process for the production of spherical graphite fuel elements
– Google Patents

GB1137939A – A process for the production of spherical graphite fuel elements
– Google Patents
A process for the production of spherical graphite fuel elements

Info

Publication number
GB1137939A

GB1137939A
GB55678/66A
GB5567866A
GB1137939A
GB 1137939 A
GB1137939 A
GB 1137939A
GB 55678/66 A
GB55678/66 A
GB 55678/66A
GB 5567866 A
GB5567866 A
GB 5567866A
GB 1137939 A
GB1137939 A
GB 1137939A
Authority
GB
United Kingdom
Prior art keywords
fuel
particles
pressing
graphite
core
Prior art date
1965-12-18
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)

Expired

Application number
GB55678/66A
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)

Nukem GmbH

Original Assignee
Nukem GmbH
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
1965-12-18
Filing date
1966-12-13
Publication date
1968-12-27

1966-12-13
Application filed by Nukem GmbH
filed
Critical
Nukem GmbH

1968-12-27
Publication of GB1137939A
publication
Critical
patent/GB1137939A/en

Status
Expired
legal-status
Critical
Current

Links

Espacenet

Global Dossier

Discuss

Classifications

G—PHYSICS

G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING

G21C—NUCLEAR REACTORS

G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements

G21C3/42—Selection of substances for use as reactor fuel

G21C3/58—Solid reactor fuel Pellets made of fissile material

G21C3/62—Ceramic fuel

G21C3/64—Ceramic dispersion fuel, e.g. cermet

G—PHYSICS

G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING

G21C—NUCLEAR REACTORS

G21C21/00—Apparatus or processes specially adapted to the manufacture of reactors or parts thereof

G21C21/02—Manufacture of fuel elements or breeder elements contained in non-active casings

Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS

Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE

Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION

Y02E30/00—Energy generation of nuclear origin

Y02E30/30—Nuclear fission reactors

Abstract

1,137,939. Moulding nuclear fuel elements. NUKEM NUKLEAR-CHEMIE UND-METALLURGIE G.m.b.H. 13 Dec., 1966 [18 Dec., 1965], No. 55678/66. Heading B5A. Spherical graphite fuel elements for use in high-temperature nuclear reactors and comprising fuel particles mixed with graphite mass and an amount of binder, are cold pressed in a silicone rubber mould within a steel pressing die, which mould is cylindrical in exterior shape and divided into two symmetrical halves axially or radially and is provided with an ellipsoidal cavity which is deformed to spherical shape during cold pressing at high pressures of up to 7 tons/cm.2 The powder is consolidated to three to five times its original density and occluded air is removed by vent grooves provided in the rubber mould and steel die or by pressing in vacuo. To protect the fuel particles on the surface from damage, the fuel particle containing element is surrounded by a thin, particle free shell of the same graphite as the matrix of the fuel containing core which is initially pre-pressed semi.hydrostatically in rubber moulds at a low pressure of 20/kg./cm.2 preferably to provide a grooved surface; the prepressed core is then enclosed within prepressed half shells of graphite powder. Improved heat dissipation from the fuel particles may be obtained with a fuel containing intermediate layer between a fuel free core and outer shell. After pressing, the binder is coked by heating the element at 1,000‹ C. in an inert gas followed by heating in vacuo at 1600 to 2,000‹ C. whereby oxidation resistance, impact strength and thermal conductivity are improved. The semi-hydrostatic pressing improves strength and isotropy over that obtained in a steel die. In addition to pure fuel particles (coated UC 2 – or UO 2 -particles), fertile material particles in which uranium is completely or partly replaced by thorium, or burnt up poison particles (with B 4 C for example) may be introduced.

GB55678/66A
1965-12-18
1966-12-13
A process for the production of spherical graphite fuel elements

Expired

GB1137939A
(en)

Applications Claiming Priority (1)

Application Number
Priority Date
Filing Date
Title

DEN0027788

1965-12-18

Publications (1)

Publication Number
Publication Date

GB1137939A
true

GB1137939A
(en)

1968-12-27

Family
ID=7344402
Family Applications (1)

Application Number
Title
Priority Date
Filing Date

GB55678/66A
Expired

GB1137939A
(en)

1965-12-18
1966-12-13
A process for the production of spherical graphite fuel elements

Country Status (5)

Country
Link

BE
(1)

BE691237A
(en)

DE
(1)

DE1646783C3
(en)

GB
(1)

GB1137939A
(en)

LU
(1)

LU52598A1
(en)

NL
(1)

NL152096B
(en)

Cited By (1)

* Cited by examiner, † Cited by third party

Publication number
Priority date
Publication date
Assignee
Title

US4826652A
(en)

*

1985-09-27
1989-05-02
Hochtemperatur-Reaktorbau Gmbh
Low capacity nuclear reactor housed underground in the cavity of a cylindrical pressure vessel

Families Citing this family (5)

* Cited by examiner, † Cited by third party

Publication number
Priority date
Publication date
Assignee
Title

DE3435863A1
(en)

*

1984-09-29
1986-04-03
Hobeg Hochtemperaturreaktor-Brennelement Gmbh, 6450 Hanau

METHOD FOR PRODUCING ISOTROPIC SPHERICAL BURNING OR ABSORBER ELEMENTS FOR HIGH TEMPERATURE REACTORS

DE3640494A1
(en)

*

1986-11-27
1988-06-09
Hobeg Hochtemperaturreaktor

SPHERICAL FUEL ELEMENT FOR HIGH TEMPERATURE REACTORS AND METHOD FOR THE PRODUCTION THEREOF

DE3807853C1
(en)

*

1988-03-10
1989-08-10
Nukem Gmbh, 6450 Hanau, De

DE19837989C2
(en)

*

1998-08-21
2000-12-21
Andrea Hrovat

Process for the production of fuel elements, absorber elements and fuel bodies for high-temperature reactors

DE10253205B4
(en)

*

2002-11-15
2005-09-15
Ald Vacuum Technologies Ag

Automated production process for the production of spherical graphite, fuel and absorber elements for high-temperature nuclear reactors (HTR)

1965

1965-12-18
DE
DE1646783A
patent/DE1646783C3/en
not_active
Expired

1966

1966-12-01
NL
NL666616941A
patent/NL152096B/en
unknown

1966-12-13
GB
GB55678/66A
patent/GB1137939A/en
not_active
Expired

1966-12-14
LU
LU52598A
patent/LU52598A1/xx
unknown

1966-12-14
BE
BE691237A
patent/BE691237A/xx
unknown

Cited By (1)

* Cited by examiner, † Cited by third party

Publication number
Priority date
Publication date
Assignee
Title

US4826652A
(en)

*

1985-09-27
1989-05-02
Hochtemperatur-Reaktorbau Gmbh
Low capacity nuclear reactor housed underground in the cavity of a cylindrical pressure vessel

Also Published As

Publication number
Publication date

LU52598A1
(en)

1967-02-14

NL6616941A
(en)

1967-06-19

NL152096B
(en)

1977-01-17

DE1646783A1
(en)

1971-09-02

DE1646783B2
(en)

1974-01-03

BE691237A
(en)

1967-05-16

DE1646783C3
(en)

1974-08-15

Similar Documents

Publication
Publication Date
Title

US10689776B2
(en)

2020-06-23

Preparation method of monocrystal uranium dioxide nuclear fuel pellets

KR101638351B1
(en)

2016-07-12

Preparation method of nuclear fuel pellet including thermal conductive metal, and the nuclear fuel pellet thereby

GB952090A
(en)

1964-03-11

Nuclear fuel element and process of making the same

CN106653126A
(en)

2017-05-10

Method and mould for preparing annular UO2 fuel pellet

US2941933A
(en)

1960-06-21

Fuel element for nuclear reactor

US3284195A
(en)

1966-11-08

Method of fabricating articles from powders

GB1137939A
(en)

1968-12-27

A process for the production of spherical graphite fuel elements

US3912798A
(en)

1975-10-14

Process for production of fuel bodies, fuel elements and absorber elements for high temperature reactors

US3996319A
(en)

1976-12-07

Process for the production of pressed block fuel elements of high power for gas cooled high temperature reactor

US3823067A
(en)

1974-07-09

Shaped nuclear fissionable bodies

US4134941A
(en)

1979-01-16

Spherical fuel elements made of graphite for temperature reactors and process for reworking it after the irradiation

US3342562A
(en)

1967-09-19

High density urania fuel elements

US3213162A
(en)

1965-10-19

Method of making nuclear fuel compact

CN110085338A
(en)

2019-08-02

UO2The preparation method and preparation facilities of/Cr hybrid fuel pellet

US3168601A
(en)

1965-02-02

Process for the production of plutonium oxide-containing nuclear fuel compacts

GB1482439A
(en)

1977-08-10

Pressed spherical fuel elements of graphite for high-temperature nuclear reactors

US3161701A
(en)

1964-12-15

Method of making nuclear fuel compact

US4045526A
(en)

1977-08-30

Process for the preparation of graphite-clad nuclear fuel rods

US3438858A
(en)

1969-04-15

Fuel elements

US3404200A
(en)

1968-10-01

Method of preparing a cermet nuclear fuel

US3763292A
(en)

1973-10-02

Manufacture of bonded particle nuclear fuel composites

US3720739A
(en)

1973-03-13

Nuclear fuel pressing process

US3168371A
(en)

1965-02-02

Process for producing high density urania fuel elements

GB1327786A
(en)

1973-08-22

Manufacture of fuel for nuclear reactors

US3668285A
(en)

1972-06-06

Warm-pressing method of making stacked fuel plates

Download PDF in English

None