CA2105764A1 - Method for processing absorber rods from water-cooled nuclear reactors - Google Patents
Method for processing absorber rods from water-cooled nuclear reactorsInfo
- Publication number
- CA2105764A1 CA2105764A1 CA002105764A CA2105764A CA2105764A1 CA 2105764 A1 CA2105764 A1 CA 2105764A1 CA 002105764 A CA002105764 A CA 002105764A CA 2105764 A CA2105764 A CA 2105764A CA 2105764 A1 CA2105764 A1 CA 2105764A1
- Authority
- CA
- Canada
- Prior art keywords
- tritium
- rods
- melt
- water
- nuclear reactors
- Prior art date
- 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.)
- Abandoned
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/34—Apparatus or processes for dismantling nuclear fuel, e.g. before reprocessing ; Apparatus or processes for dismantling strings of spent fuel elements
- G21C19/38—Chemical means only
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/28—Treating solids
- G21F9/30—Processing
- G21F9/32—Processing by incineration
-
- 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
Landscapes
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- General Chemical & Material Sciences (AREA)
- Plasma & Fusion (AREA)
- Environmental & Geological Engineering (AREA)
- Manufacture And Refinement Of Metals (AREA)
- Solid-Sorbent Or Filter-Aiding Compositions (AREA)
- Catalysts (AREA)
Abstract
A process is disclosed for processing absorber rods made of steel tubes filled with boron compounds suitable for compact and safe terminal storage of radioactive materials. The rods are immersed in a molten bath composed of iron, nickel, chromium or manganese, in an oxygen-free atmosphere, and maintained at a temperature above 1500 ·C, releasing the tritium contained in the tubes. The tritium is then removed with an inert sweeping gas and bonded in a tritium trap. A tritium-free monolithic block is thus obtained, containing metal borides and carbides and capable of being terminally stored.
Description
2i~7~
Fo 2314 A method for processing absorber rods from water-cooled nuclear reactors The invention relates to a method for processing absorber rods with respect to the compact and safe final stor-age of radioactive materials, these rods being shaped as steel tubes filled with boron compounds.
In water-cooled nuclear reactors, for example boiling water reactors, the reactivity control is carried out by means of rods made of steel tubes, for example of the type AISI 304 or 306, which are filled with boron compounds, in particular B4C (boron carbide).
This method uses the neutron absorption features of the 10B-iqotope. In interactions wi-th thermal neutrons, this isotope then creates 7L,i, which its~l reacts with fast neu-trons and forms tritium 3H.
In order to simplify the descrlption, tritium will be referenced hereinafter T and tritium water, in which part of the normal hydrogen atoms are replaced by tritium atoms, is referenced HT0.
The isotope 18 itself reacts also with fast neutrons, thus directly creating ~. The following nuclear reactions are the result:
IB ~ ln (thermal) ~ 7Li + 4He 7Li + ln (fast) -, T ~ 4He ~ n B ~ ln (fast) ~ T ~ 24He Typical dimensions of such rods in a boiling water reactor are:
inner diameter 4,7 mm thickness of wall . 0,67 mm total length ca. 2900 mm material SS AISI 304 filling 47 g of B4C
Due to a vibrating system, this filLing reaches a 7 ~ l~
density of about 70~ of the theoretical density of boron car-bide. After the filling, the tube is evacuated and sealed. In a typical boiling water reactor there are 4140 rods, i.e. a total amount of 194 kg boron carbide.
After three years of operation in a boiling water reactor, such a rod contains, besides the radioactive activat-ing products usually resulting from neutron bombing of the metal, a tritium contents equivalent to of 0,85 Ci.
This tritium is mainly present in the boron carbide matrix. About 6 per mille of the total tritium quantity is contained in the envelope material of the rod and an even smaller part~of about 0,2 per mille is present in the residual gas volume inside the rod.
Since the crystalline structure of B4C has remained unchanged in spite of the interactions with the neutrons, the tritium thus created can be bound inside the structure in several manners:
The most probable are depositions in the interspaces of the ikosaedric crystals of the boron carbide and an intrin-sic strong covalent chemical bonding. This fact confers to the tritium an extraordinary stability, so that it is only released by the boron carbide at temperatures above 700C in an oxygen-free atmosphere. In fact, the presence of oxygen, even with concentrations of only 50 ppm, influences the release of tritium, since a partial oxidation of the carbide occurs, which leads to the superficial formation of a vitreous boron hydride layer, which finally retards the release.
In practice, these absorber rods cannot be prepared for final storage like a normal metal radioac-tive waste prod-uct, for example by mechanical crushing and/or compacting.
Firstly, the boron carbide has become very brittle by the interactions with the neutrons and thus has become very frag-ile. Secondly, the container tubes have hair cracks whic result on the one hand from the interactions of the boron carbide with the metallic material of the rods and on the 2~5~
other hand from the pressure created by the gas contained inside the rods, or finally also from a deposition of the boron carbide during the neutron impact and thus from a swell-in~ inside the rod connected therewith. Furthermore, the waste removal is particularly complicated by the not negligible presence of tritium.
Up to now, no appropriate solution has been found for compacting such absorber rods with respect to a terminal stor-age, since the risk of a propagation of the boron carbicle and thus a release of the radioactive products connected therewith could not be excluded. In fact, the boron carbide is so britt-le after irradiation and so little water-resistant, that the decomposition of boron carbide leads to a fine dispersion of powdery radioactive material.
It is thus the aim of the invention to indicate such a method which leads to a waste product which can be finally ~tored with a significantly reduced volume. Furthermore, this method is supposed to reduce the risk of an uncontrolled dis-semination of the radioactivity contained in the rods, due to by the fact that mechanical steps like sawing are not necess-ary.
This problem is solved by the method according to claim 1. As for features of preferred embodiments of the invention, which refer in particular to the simultaneous sep-aration and collection of the total tritium contents, refer-ence is made to the sub-claims.
The invention will now be described more in detail with reference to several embodiments of this method.
Example 1 In an electrically heated furnace a melt of iron is obtained in a melting pot made of sintered alumina. The gas volume above the melt is continuously swept with an inert gas, for example argon. The temperature of the melt is brought to at least 1500C and is maintained at this temperature. Then the end of an absorption rod to be processed of the type 7 ~ ~
referred to above is introduced into the melt and is advanced in accordance with the melting speed. The temperature of the melt is chosen high enough so that the envelope material of the rod melts and thus the boron carbide can be exposed to the influence of the iron of the melt, a low melting eutecticum being thus formed. The sweeping with argon avoids oxidation of the boron, because boron oxide would be volatile at the tem-perature of the melt.
For the separation of tritium, which mounts in elemen-tary form (HT) as well as in oxide form (HTO) and which is conveyed away by the sweeping gas, the method can be adopted which is also in use in the technology of fusion reactors for totally converting HT into HTO by means of a catalyst at tem-peratures of some hundred degrees Celsius, followed by a sep-aration of water molecules at ambient temperature by means of molecular sieves (or zeolites). This step is known per se, for example from Proceedings of the International Conference on Tritium Technology in Fission, Fusion and Isotopic Applica-tion~, Toronto/Canada, 1 to 6 May 1988, see "Europ. Tritium Handling Experimental Laboratory" E. Vassallo, J. Bourdon, H.
Dworschak, D. Pugh.
After cooling the melt, a compact monolithic mass is obtained in the pot which, during examination by means of X-ray fluorescence analysis, shows the presence of eutectic ternary iron compounds like Fe3C, ~e2B, FeC, FeB, as well as the presence of carbides and borides of different stoichiometry of nickel, chromium and iron. This monolith can be finally stored without problem.
Example 2 The melt is prepared in a pot of zirconium oxide which is placed in an electromagnetic induction furnace. The furnace is made of a quartz tu~e which is surrounded by an induction winding and connected at its two ends to a sweeping circuit.
The temperature of the melt is 1550C. A few minutes after the introduction of the rod to be melted, a homogenous mass is ~1337~1 practically excluded.
7 ~ '~
obtained which, after cooling of the furnace, is converted into a monolithic compact material, the analysis of which resembles that of example 1.
Example 3 Instead of iron, the same amount of nickel is used for the original melt. In this case, the result is preponderantly nickel boride, but also iron and chromium borides respectively carbides occur.
ExamPle 4 The iron of the original melt is replaced by cobalt.
The result is preponderan-tly cobalt boride as well as the usual Fe-Ni-borides respectively carbide.
The speed of the cooling ~f the melt after introduc-tion of the rod has almost no influence on the result, which was confirmed by a comparison of a fast cooling phase (a few minutes under increased sweep gas flow) with a natural cooling phase over more than 12 hours.
Also other pot materials, in particular pots made of graphite are well adapted, but also pots of other high melting point metals such as for example Ti, V, Zrj Mo, Hf, Ta, W, Pt, Pd, which are covered with an inner layer of 5 mm of graphite or alumina or zircona.
With the described method, also integral absorber elements can be processed, which consist of a central guiding rod made of steel SS AISI 304 and double-walled plates sol-dered thereto in cross-shape. Between these plates are dis-posed in adjacent longitudinal rows of the rod fifteen of the above mentioned absorber rods. In order to obtain a better ratio between the material to be introduced into the ~urnace and the diameter of the furnace, it can be useful to cut the plates off the guiding rod before melting them. Due to the fact that the first rod close to the guiding rod does not contain in general any boron carbide, with an appropriate choice of the cutting device, damaging of boron carbide con-taining rods and thus undesirably releasing this material is
Fo 2314 A method for processing absorber rods from water-cooled nuclear reactors The invention relates to a method for processing absorber rods with respect to the compact and safe final stor-age of radioactive materials, these rods being shaped as steel tubes filled with boron compounds.
In water-cooled nuclear reactors, for example boiling water reactors, the reactivity control is carried out by means of rods made of steel tubes, for example of the type AISI 304 or 306, which are filled with boron compounds, in particular B4C (boron carbide).
This method uses the neutron absorption features of the 10B-iqotope. In interactions wi-th thermal neutrons, this isotope then creates 7L,i, which its~l reacts with fast neu-trons and forms tritium 3H.
In order to simplify the descrlption, tritium will be referenced hereinafter T and tritium water, in which part of the normal hydrogen atoms are replaced by tritium atoms, is referenced HT0.
The isotope 18 itself reacts also with fast neutrons, thus directly creating ~. The following nuclear reactions are the result:
IB ~ ln (thermal) ~ 7Li + 4He 7Li + ln (fast) -, T ~ 4He ~ n B ~ ln (fast) ~ T ~ 24He Typical dimensions of such rods in a boiling water reactor are:
inner diameter 4,7 mm thickness of wall . 0,67 mm total length ca. 2900 mm material SS AISI 304 filling 47 g of B4C
Due to a vibrating system, this filLing reaches a 7 ~ l~
density of about 70~ of the theoretical density of boron car-bide. After the filling, the tube is evacuated and sealed. In a typical boiling water reactor there are 4140 rods, i.e. a total amount of 194 kg boron carbide.
After three years of operation in a boiling water reactor, such a rod contains, besides the radioactive activat-ing products usually resulting from neutron bombing of the metal, a tritium contents equivalent to of 0,85 Ci.
This tritium is mainly present in the boron carbide matrix. About 6 per mille of the total tritium quantity is contained in the envelope material of the rod and an even smaller part~of about 0,2 per mille is present in the residual gas volume inside the rod.
Since the crystalline structure of B4C has remained unchanged in spite of the interactions with the neutrons, the tritium thus created can be bound inside the structure in several manners:
The most probable are depositions in the interspaces of the ikosaedric crystals of the boron carbide and an intrin-sic strong covalent chemical bonding. This fact confers to the tritium an extraordinary stability, so that it is only released by the boron carbide at temperatures above 700C in an oxygen-free atmosphere. In fact, the presence of oxygen, even with concentrations of only 50 ppm, influences the release of tritium, since a partial oxidation of the carbide occurs, which leads to the superficial formation of a vitreous boron hydride layer, which finally retards the release.
In practice, these absorber rods cannot be prepared for final storage like a normal metal radioac-tive waste prod-uct, for example by mechanical crushing and/or compacting.
Firstly, the boron carbide has become very brittle by the interactions with the neutrons and thus has become very frag-ile. Secondly, the container tubes have hair cracks whic result on the one hand from the interactions of the boron carbide with the metallic material of the rods and on the 2~5~
other hand from the pressure created by the gas contained inside the rods, or finally also from a deposition of the boron carbide during the neutron impact and thus from a swell-in~ inside the rod connected therewith. Furthermore, the waste removal is particularly complicated by the not negligible presence of tritium.
Up to now, no appropriate solution has been found for compacting such absorber rods with respect to a terminal stor-age, since the risk of a propagation of the boron carbicle and thus a release of the radioactive products connected therewith could not be excluded. In fact, the boron carbide is so britt-le after irradiation and so little water-resistant, that the decomposition of boron carbide leads to a fine dispersion of powdery radioactive material.
It is thus the aim of the invention to indicate such a method which leads to a waste product which can be finally ~tored with a significantly reduced volume. Furthermore, this method is supposed to reduce the risk of an uncontrolled dis-semination of the radioactivity contained in the rods, due to by the fact that mechanical steps like sawing are not necess-ary.
This problem is solved by the method according to claim 1. As for features of preferred embodiments of the invention, which refer in particular to the simultaneous sep-aration and collection of the total tritium contents, refer-ence is made to the sub-claims.
The invention will now be described more in detail with reference to several embodiments of this method.
Example 1 In an electrically heated furnace a melt of iron is obtained in a melting pot made of sintered alumina. The gas volume above the melt is continuously swept with an inert gas, for example argon. The temperature of the melt is brought to at least 1500C and is maintained at this temperature. Then the end of an absorption rod to be processed of the type 7 ~ ~
referred to above is introduced into the melt and is advanced in accordance with the melting speed. The temperature of the melt is chosen high enough so that the envelope material of the rod melts and thus the boron carbide can be exposed to the influence of the iron of the melt, a low melting eutecticum being thus formed. The sweeping with argon avoids oxidation of the boron, because boron oxide would be volatile at the tem-perature of the melt.
For the separation of tritium, which mounts in elemen-tary form (HT) as well as in oxide form (HTO) and which is conveyed away by the sweeping gas, the method can be adopted which is also in use in the technology of fusion reactors for totally converting HT into HTO by means of a catalyst at tem-peratures of some hundred degrees Celsius, followed by a sep-aration of water molecules at ambient temperature by means of molecular sieves (or zeolites). This step is known per se, for example from Proceedings of the International Conference on Tritium Technology in Fission, Fusion and Isotopic Applica-tion~, Toronto/Canada, 1 to 6 May 1988, see "Europ. Tritium Handling Experimental Laboratory" E. Vassallo, J. Bourdon, H.
Dworschak, D. Pugh.
After cooling the melt, a compact monolithic mass is obtained in the pot which, during examination by means of X-ray fluorescence analysis, shows the presence of eutectic ternary iron compounds like Fe3C, ~e2B, FeC, FeB, as well as the presence of carbides and borides of different stoichiometry of nickel, chromium and iron. This monolith can be finally stored without problem.
Example 2 The melt is prepared in a pot of zirconium oxide which is placed in an electromagnetic induction furnace. The furnace is made of a quartz tu~e which is surrounded by an induction winding and connected at its two ends to a sweeping circuit.
The temperature of the melt is 1550C. A few minutes after the introduction of the rod to be melted, a homogenous mass is ~1337~1 practically excluded.
7 ~ '~
obtained which, after cooling of the furnace, is converted into a monolithic compact material, the analysis of which resembles that of example 1.
Example 3 Instead of iron, the same amount of nickel is used for the original melt. In this case, the result is preponderantly nickel boride, but also iron and chromium borides respectively carbides occur.
ExamPle 4 The iron of the original melt is replaced by cobalt.
The result is preponderan-tly cobalt boride as well as the usual Fe-Ni-borides respectively carbide.
The speed of the cooling ~f the melt after introduc-tion of the rod has almost no influence on the result, which was confirmed by a comparison of a fast cooling phase (a few minutes under increased sweep gas flow) with a natural cooling phase over more than 12 hours.
Also other pot materials, in particular pots made of graphite are well adapted, but also pots of other high melting point metals such as for example Ti, V, Zrj Mo, Hf, Ta, W, Pt, Pd, which are covered with an inner layer of 5 mm of graphite or alumina or zircona.
With the described method, also integral absorber elements can be processed, which consist of a central guiding rod made of steel SS AISI 304 and double-walled plates sol-dered thereto in cross-shape. Between these plates are dis-posed in adjacent longitudinal rows of the rod fifteen of the above mentioned absorber rods. In order to obtain a better ratio between the material to be introduced into the ~urnace and the diameter of the furnace, it can be useful to cut the plates off the guiding rod before melting them. Due to the fact that the first rod close to the guiding rod does not contain in general any boron carbide, with an appropriate choice of the cutting device, damaging of boron carbide con-taining rods and thus undesirably releasing this material is
Claims (3)
1. A method for processing absorber rods from water-cooled nuclear reactors in view of the compact and safe final storage of radioactive materials, the rods being steel tubes filled with boron compounds, characterized in that the rods are introduced under an oxygen-free atmosphere into a melting bath, which consists essentially of iron or nickel or chromium or mangan and which is maintained at a temperature above 1500°C.
2. A method according to claim 1, characterized in that the free gas volume above the melt is swept with an inert gas.
3. A method according to claim 2, characterized in that after the passage through the free gas volume above the melt, the sweeping gas is supplied to a tritium trap.
Applications Claiming Priority (3)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| LU87907A LU87907A1 (en) | 1991-03-13 | 1991-03-13 | METHOD FOR REPROCESSING ABSORBER BARS FROM WATER-COOLED CORE REACTORS |
| LU87907 | 1991-03-13 | ||
| PCT/EP1992/000526 WO1992016948A1 (en) | 1991-03-13 | 1992-03-10 | Process for processing absorber rods from water-cooled nuclear reactors |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CA2105764A1 true CA2105764A1 (en) | 1992-09-14 |
Family
ID=19731283
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CA002105764A Abandoned CA2105764A1 (en) | 1991-03-13 | 1992-03-10 | Method for processing absorber rods from water-cooled nuclear reactors |
Country Status (5)
| Country | Link |
|---|---|
| EP (2) | EP0575420A1 (en) |
| JP (1) | JPH06505797A (en) |
| CA (1) | CA2105764A1 (en) |
| LU (1) | LU87907A1 (en) |
| WO (1) | WO1992016948A1 (en) |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB9823046D0 (en) * | 1998-10-22 | 1998-12-16 | British Nuclear Fuels Plc | Electrochemical dissolution |
| CN114113188B (en) * | 2021-10-12 | 2023-03-03 | 四川大学 | Efficient tritium analysis method, device, equipment and storage medium |
Family Cites Families (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4417790A (en) * | 1979-05-10 | 1983-11-29 | American Optical Corporation | Finished ophthalmic lens comprising an optical smooth coating over a rough-surfaced base |
| FR2583208B1 (en) * | 1985-06-07 | 1992-04-24 | Commissariat Energie Atomique | PROCESS AND DEVICE FOR THE TREATMENT OF NON-ORGANIC SOLID TRITY WASTE |
| DE3930420C1 (en) * | 1989-09-12 | 1990-11-22 | Bundesrepublik Deutschland, Vertreten Durch Den Bundesminister Der Verteidigung, Dieser Vertreten Durch Den Praesidenten Des Bundesamtes Fuer Wehrtechnik Und Beschaffung, 5400 Koblenz, De | Radioactive waste tritium sepn. - by flushing in gas flow with oxygen, heating and passing tritium through water |
-
1991
- 1991-03-13 LU LU87907A patent/LU87907A1/en unknown
-
1992
- 1992-03-10 JP JP4505804A patent/JPH06505797A/en active Pending
- 1992-03-10 WO PCT/EP1992/000526 patent/WO1992016948A1/en not_active Application Discontinuation
- 1992-03-10 CA CA002105764A patent/CA2105764A1/en not_active Abandoned
- 1992-03-10 EP EP92906452A patent/EP0575420A1/en not_active Withdrawn
- 1992-03-10 EP EP92104071A patent/EP0503557A1/en not_active Withdrawn
Also Published As
| Publication number | Publication date |
|---|---|
| EP0503557A1 (en) | 1992-09-16 |
| JPH06505797A (en) | 1994-06-30 |
| EP0575420A1 (en) | 1993-12-29 |
| LU87907A1 (en) | 1992-11-16 |
| WO1992016948A1 (en) | 1992-10-01 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| JP2543973B2 (en) | Fuel element with oxidation resistant coating | |
| Frost | The carbides of uranium | |
| US3899392A (en) | Nuclear fuel element containing particles of an alloyed Zr, Ti and Ni getter material | |
| CA2105764A1 (en) | Method for processing absorber rods from water-cooled nuclear reactors | |
| Kobisk et al. | Conversion of isotope compounds to metals by reduction-distillation methods | |
| Bottomley et al. | Metallurgical examination of bore samples from the Three Mile Island unit 2 reactor core | |
| JPH0827388B2 (en) | Heat resistant radiation shielding material | |
| Cowen | Boron and boron-containing materials | |
| US3219541A (en) | Method of preventing carburization of fuel element cladding metals by uranium carbide fuels | |
| Dayton et al. | Progress Relating to Civilian Applications During August, 1959 | |
| Dayton et al. | Progress Relating to Civilian Applications During April, 1960 | |
| Cashin | Silica‐Uranium Fuel Systems | |
| Johnson Jr et al. | Tritium production from ceramic targets: a summary of the Hanford Coproduct Program | |
| Porter et al. | Neutron irradiation and compatibility testing of Li2O | |
| Talbot et al. | Tritium sorption in lithium-bismuth and lithium-aluminum alloys | |
| Stanaway et al. | The solubility of transition metals, Mn and Co in liquid sodium | |
| Morrison | FEATURE ARTICLE The Behavior of Fission Gases Gases in Ceramic Reactor Materials...... | |
| Terai et al. | Tritium release behavior from liquid tritium breeding materials for fusion reactor blanket under neutron irradiation | |
| Tingey et al. | Solid state containment of noble gases in sputter deposited metals and low density glasses | |
| HOYT | General Electric Company Vallecitos Atomic Laboratory Pleasanton, California | |
| van Vucht | X-RAY DIFFRACTION OF Th $ sub 2$ Al CONTAINING HYDROGEN | |
| Poole et al. | Properties of some plutonium fuels | |
| Strasser et al. | CARBIDE FUEL DEVELOPMENT. Phase V Report, October 1, 1962-September 30, 1963 | |
| Godshall et al. | Development of a CbC--ZrC material for use as a hot hardness indenter | |
| Tingey et al. | Solid state storage of radioactive krypton in a silica matrix |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| FZDE | Dead |