WO1986002770A1

WO1986002770A1 - Method for disposal of radioactive wastes

Info

Publication number: WO1986002770A1
Application number: PCT/US1985/002058
Authority: WO
Inventors: William J. Hagerty
Original assignee: Inventive Processing Company
Priority date: 1984-10-24
Filing date: 1985-10-22
Publication date: 1986-05-09
Also published as: EP0197146A1

Abstract

A process for chemically disposing of low-level and high-level radioactive waste including containment and processing radioactive materials in a solution and radioactive particle matter within any type of nuclear explosion. This is primary means of providing chemical protection from all harmful radiation, the object and intent is to provide a source of complete and safe disposal, that will eliminate any need for burial or waste sites anywhere in the world. The process and series of methods in a step by step method as described herein in the claims and describe the state-of-the-art technology set-forth by the examples herein this application. The process and methods described will provide safe protection and complete disposal of any low-level and high-level radiation fall-out from within any type nuclear explosion such as a nuclear power plant or other radiation, from other nuclear explosions. The high-level radiation will not escape the explosion zone or site, because the particle matter is no longer radioactive material. The process and treatment methods will provide a safe method for disposal through evaporation that will not harm the environment. Certain other examples of the subject matter are not described within, because of possible national security matters or possible defense applications in regard to the subject matter not described herein. This process will produce a chemical reaction and energy, for the reduction and deterioration of all radiation within, radioactive material, of any nature anywhere in the world to protect the environment, this process will allow the reclaiming of present burial or waste sites for safe and complete disposal.

Description

METHOD FOR DISPOSAL OF RADIOACTIVE WASTES CROSS-REFERENCE TO RELATED APPLICATION

THIS APPLICATION IS A CONTINUATION-IN-PART APPLICATION OF COPENDING APPLICATION SERIAL NO. 423,831 , FILED SEPTEMBER 27 , 1932 , AND NOW ABANDONED.

BACKGROUND OF THE INVENTION

FIELD OF THE INVENTION :

THIS INVENTION RELATES TO THE COMPLETE DISPOSAL OF LLRW , RADIOACTIVE WASTES , AND MORE PARTICULARLY , TO THE DISPOSAL OF RADIOACTIVE WASTES BY CHEMICAL PROCESSES,

DESCRIPTION OF THE PRIOR ART :

LLRW - RADIOACTIVE WASTE DISPOSAL IS ACCOMPLISHED BY THE PROGRESSIVE HALF-LIFE DECAY OF THE RADIOACTIVE MATERIAL. SINCE THE HALF-LIFE OF RADIOACTIVE ISOTOPES DO VARY FROM A FRACTION OF A SECOND TO MANY MILLENIA . THE PRIMARY MEANS OF PROVIDING PROTECTION FROM HARMFUL RADIOACTIVITY IS TO PROVIDE AN ELEMENT OF SUBSTANCE THAT IS CAPABLE OF COMPLETE DISPOSAL AND CONTAIN THE RADIOACTIVE MATERIAL WITHIN THE CHEMICAL PROCESS , WHETHER THEY BE ALPHA RAYS , BETA RAYS OR GAMMA RAYS. THIS IS AN VIABLE ALTERNATE TO WAITING FOR THE NATURAL DECAY OF RADIOACTIVE LLRW

AND HLW MATERIALS AND ISOTOPES TO A STABLE UNIT OR ELEMENT. AN

ALPHA PARTICLE IS A HELIUM ATOM NUCLEUS. IT IS COMPOSED OF TWO PROTONS AND TWO NEUTRONS. ALPHA PARTICLES ARE THE LEAST PENTKΛR ING OF THE THREE COMMON FORMS OF RADIATION. BETA PARTICLES , WHEN NEGATIVELY CHARGED , ARE PHYSICALLY IDENTICAL TO ELECTRONS. POSTIVE BETA PARTICLES ARE CALLED POSI¬TRONS. BETA RADIATION MAY CAUSE SKIN BURNS , AND BETA EMITTERS ARE HARMFUL IF THEY ARE INHALED , AS ARE. ALPHA PARTICLES OR ALPHA EMITTING SUBSTANCES. GAMMA RAYS ARE THE MOST HARMFUL FORM OF RADIATION, THE LESS THE AMOUNT OF GAMMA RADIATION GIVEN OFF BY A SUBSTANCE , THE LESS THE DANGER FOR HUMANS . WHEN WORKING WITH THE SUBSTANCES, WLTH ENERGY SHORTAGES EXISTING PRESENTLY , AND FORECAST TO BE MORE ACUTE IN COMING YEARS , THE NATIONS OF THE WORLD ARE TURNING MORE TO NUCLEAR ENERGY TO REPLACE GAS AND OIL FOR GENERATING ELECTRICAL ENERGY. A PRODUCT OF THE USE OF NUCLEAR ENERGY , OR RATHER , A BY-PRODUCT , IS RADIOACTIVE WASTE , INCLUDING COMTAMINATED CLOTHING , FILTERS , GENERAL TRASH , AS WELL AS DEPLETED FUEL

RODS , AND ETC, IN THE MEDICAL FIELD , THERE ARE MEDICAL WASTES

GENERATED FROM NUCLEAR MEDICINE , SUCH AS COBALT 60 AND CESIUM 137. THE DISPOSAL OF THE RADIOACTIVE WASTE IS OF PARAMOUNT

CONCERN TO EVERYONE . MORE PARTICULARLY , WHEN THE GAMMA RADIATION AND OTHER EMITTERS ARE PROCESSED BY CHEMICAL METHODS , THAT WILL ELIMINATE THE RADIATION AND PROVIDE A SAFE METHOD OF DISPOSAL THAT WILL ELIMINATE THE NEED FOR ANY BURIAL OR WASTE SITES , THE WASTE PROBLEM IS SIMPLIFIED IMMENSELY.

WHEN THE RADIOACTIVE WASTE MATERIAL . WHICH HAS A MAXIMUM OUTPUT OF GAMMA RADIATION , IS PROCESSED BY CHEMICAL METHODS WHICH ARE CAPBLE OF TREATMENT FOR COMPLETE DISPOSAL , SUCH RADIOACTIVE MATERIAL WILL NO LONGER POSE A THREAT TO THE MAN KIND OR THE ENVIRONMENT. SINCE GAMMA RADIATION IS SUBSTANTIALLY MORE DIFFICULT TO TREAT OR PROCESS THAN ARE THE ALPHA AND OR BETA RADIATION , DIFFERENT PROBLEMS RESULT FROM ATTEMPTS TO PROVIDE BY CHEMICAL MEANS FOR THE TREATMENT AND PROCESSING OF THE RADIONUCLIDES WHICH EMIT GAMMA RADIATION , BUT THIS PROBLEM WAS OVER COME BY OTHER METHODS OF PROCESSING AND TREATMENT FOR DISPOSAL. IN THE PRIOR ART , U.S. PATENT 3,961,399 DESCRIBES A METHOD FOR CHEMICALLY ABSORBING RADIATION BY ABSORBING THE RADIOACTIVE MATERIAL CHEMICALLY IN MIXTURES OF BARIUM SULFATE , CEMENT AND BENTONITE , BUT THE MATERIAL IS STILL RADIOACTIVE THE METHOD IS FOR CONTAINMENT ONLY NOT COMPLETE DISPOSAL OF THE RADIATION FROM WITHIN THE WASTE MATERIALS AFTER PROCESSING.

U.S. PATENT 3,988,258 ALSO DEALS WITH DISPOSAL IN THE

FORM OF CONTAINMENT , BY INCORPORATING THE WASTE IN A BINDING AGENT , TO WHICH A ALKALI MATERIAL IS ADDED , BUT THE WASTE MATERIAL IS STILL RADIOACTIVE , NO REDUCTION OF THE RADIATION IS CLAIMED OR TEACHING THEREOF AS PRIOR ART.

THE EMPLOYMENT OF ACIDS WITH RESPECT TO RADIATION AND RADIOACTIVE MATERIALS , SUCH AS VARIOUS TYPES OF URANIUM ORES HAS BEEN PRIMARILY FOR THE PURPOSE OF REFINING THE ORES , PURIFY AND SEPARATION OF THE RADIOACTIVE PRODUCT WITHIN THE ORE. EXAMPLE OF ACIDS , OF VAROIUS TYPES FOR SUCH ARE ILLUSTRATED IN U.S.

PATENT 657,955 , U.S. PATENT 1,001,480 , U.S. PATENT 2,270,445 , U.S. PATENT 3,411,883 , U.S. PATENT 3,451,940 , U.S. PATENT 3, 801,701 AND U.S. PATENT 3,819,231 , TEACHES ALKALINE LEACHING OF OF URANIUM , EMPLOYING THE USE OF VAROIUS ACIDS , IS SHOWN IN

U.S. PATENT 4,092,399 , HEREIN THE ABOVE U.S. PATENTS DO NOT

TEACH OR CLAIM COMPLETE DETEROI RATION OF THE RADIATION WITHIN THE RADIOACTIVE MATERIALS DESCRIBED THEREIN.

A PUBLICATION , URANIUM PRODUCTION TECHNOLOGY , IN (1959) BY HARRINGTON AND RUEHLE , PUBLISHED BY VAN NOSTRAND COMPANY , IN INCLUDES INCOMPLETE AND SOME INFORMATION ON THE CONTROL OF HEALTH HAZARDS OF RADIATION, THIS IS PRIMARILY FOUND IN CHAPTER 13, TABLE 18.4 PROVIDES AN ABRIDGED TABLE SHOWING THE RADIOACTIVE DECAY OF URANIUM DOWN TO ITS STABLE END PRODUCT , RADIUM G. THE TABLE ALSO PROVIDES THE HALF-LIFE AND THE TYPE OF RADIATION EMISSION FOR THE VAROIUS DECAY PRODUCTS , AS INDICATED ABOVE , GAMMA RAYS ARE THE MOST PENETRATING AND ACCORDINGLY THE MOST DANDEROUS OF THE RADIATION FORMS, SOME OF THE DAUGHTERS OF RADON ARE GAMMA RAY EMITTERS, IF THE RADON IS REMOVED AS A GAS ,THE GAMMA ACTIVITY DECREASES SUBSTANTIALLY BECAUSE THE HALF-LIFE OF THE DAUGHTERS IS RELATIVELY SHORT, HOWEVER AS MORE RADON ACCUMULATES , THE GAMMA ACTIVITY BUILDS UP AGAIN , EQUILIBIUM AMOUNTS ARE REACHED IN A MATTER OF A FEW DAYS , BUT THIS CAN ONLY HAPPEN IF THERE IS A BREAK IN THE CHAIN OF THE REACTION WHICH DEMONSTRATES THAT THERE IS NO CONTROL OF THE METHOD AND PROCESS SETFORTH IN THE HARRINGTON AND RUEHLE TECHNOLOGY, THE PRESENT PROCESSES AND METHODS DESCRIBED IN THIS INVENTION HAVE BEEN LABORATORY TESTED AFTER MANY DAYS AND WEEKS AND NO SIGNIFICANT AMOUNTS OF RADIATION HAS BEEN DETECTED. IN THE HARRINGTON AND RUEHLE ARTICLE AS DESCRIBED , AFTER THE PROCESS , THE RADIATION EQUILBRIUM STILL REMAINS AT (10%) , THE METHODS DO NOT TEACH COMPLETE DISPOSAL OF THE RADIATION, OUR TESTING INDICATES THAT THE PROCESSES DO MORE THAN MERELY RELEASE RADON AND THUS DISPEL THE RADIATION ONLY TEMPORARILY , SINCE THE ELAPSED TIME IS MORE THAN ADEQUATE FOR THE RADON TO

ACCUMULATE AND TO THUS RESTORE GAMMA ACTIVITY TO NEAR EQUILIBRIUM AMOUNTS. THE HARRINGTON AND RUEHLE ARTICLE FURTHER STATES AND DESCRIBES , THAT IF RADIUM IS REMOVED FROM THE SERIES DESCRIBED IN TABLE 18,4 , THE GAMMA ACTIVITY DOES NOT REAPPEAR IN ANY PRACTICAL LENGTH OF TIME , BECAUSE THE HALF-LIFE OF RADIUM IS 1.62 x 10³ YEARS. THE ARTICALE ALSO STATES THAT IF THE PROCESS

THAT BREAKS THE CHAIN CEASES , THE RADIOACTIVE EQUILIBRIUM WILL BE RESTORED AT A RATE DEPENDING ON THE HALF-LIFE OF THE ELEMENTS AT A.rD BELOW THE BREAK. THE PROCESS DESCRIBED IS BY BOILING URANIUM ORE WITH HOT NITRIC ACID , TO REMOVE RADON ONLY TO ABOUT ( 10% ) OF THE RADIOACTIVE EQUILIBRIUM. THIS ACTION DESCRIBES THE BREAK IN THE CHAIN OF THE PROCESS , THAT WILL ALLOW THE RADIOACTIVE EQUILIBRIUM TO BE RESTORED IN A FEW HOURS TO A FEW DAYS, THIS ACTION DESCRIBES THAT THE PROCEDURES AND PROCESSES OF DIGESTION , BY BOILING IN NITRIC ACID IS COMPLETELY INADEQUATE AND CAN NOT BE DESCRIBED OR CONSIDERED AS PRIOR ART , WITH NO CONTROL OVER THE PROCESS.

WHILE IT IS KNOWN IN THE PRIOR ART TO USE ACIDS IN REFINING PROCESSES , NOTHING IN THE PRIOR ART TEACHES THE COMBINATION OF ACIDS AND BASES , AND THE PARTICULAR STEPS EMPLOYED IN THE PRESE INVENTION WHICH DEMONSTRATES COMPLETE DISPOSAL OF THE RADIATION WHILE THE OTHERS TEACH ONLY VOLUME REDUCTION AND TEMPORARY CONTAINMENT.

SUMMARY OF THE INVENTION

THE INVENTION DESCRIBED AND CLAIMED HEREIN COMPRISES THE CHEMICAL TREATMENT OF RADIOACTIVE MATERIALS TO REDUCE THE RADIOACTIVE ENERGY EMITTED BY THE RADIOACTIVE MATERIALS BY TREATING THE RADIOACTIVE MATERIALS IN A SOLUTION AND SOLUTIONS OF STRONG ACIDS , ONE OF WHICH ACIDS INCLUDES CHLORINE AFTER AND UPON CONTACT WITH SULFURIC ACID. THE ACIDS MAY BE NEUTRALIZED FOR

DISPOSAL WITH SODIUM CARBONATE , BY ADDING THE SODIUM CARBONATE TO CONTROL THE ACID SOLUTIONS , TO CONTROL THE PH LEVEL AFTER TREATMENT, A CHLORINE COMPOUND SUCH AS SODIUM HYPOCHLORITE , POWDER OR POWDER IN SOLUTIONS , IS ADDED TO THE WASTE EFFLUENT PRIOR TO THE NEUTRALIZING PROCESS. THE DIGESTION OR CONVERSION OF ANY SOLID WASTE MATERIALS HAS NO EFFECT ON THE REDUCTION OF THE RADIATION FROM WITHIN THE WASTE MATERIALS DURING PROCESSING, THE MATERIAL OF (80%) URANIUM , RADIONUCL IDES CESIUM 137 AND COBALT 60 , IN LIQUID FORM AND CONTAMINANTED COLTHING , AND WAS ALSO INCLUDED IN THE ASH MATERIALS PROCESSED. AMONG THE OBJECTS OF THE PRESENT INVENTION AS FOLLOWS :

TO PROVIDE A NEW AND USEFUL PROCESS FOR THE TOTAL REDUCTION OF HARMFUL RADIOACTIVE AND RADIATION ENERGY ;

TO PROVIDE A NEW AND USEFUL CHEMICAL PROCESS FOR REDUCTION AND DETERIORATION OF THE RADIOACTIVE ENERGY BY PROVIDING AN ACID ENVIRONMENT FOR THE PRODUCTS OF RADIOACTIVE WASTE MATERIALS:

TO PROVIDE A NEW AND USEFUL PROCESS FOR THE CONTAINMENT AND PROCESS FOR DETERIORATION OF THE RADIATION AND RADIOACTIVE MATERIALS FROM ANY TYPE OF NUCLEAR EXPLOSION WITH ANY RADIATION ENERGY AND RADIATION EMISSIONS;

TO PROVIDE A NEW AND USEFUL PROCESS FOR DETERIORATION OF ANY RADIOACTIVE MATERIALS , FOR COMPLETE DISPOSAL;

TO PROVIDE A NEW AND USEFUL PROCESS FOR DETERIORATION OF ANY RADIATION , WHICH WILL ELIMINATE THE NEED FOR ANY BURIAL AND OR WASTE DUMP SITES;

TO PROVIDE A NEW AND USEFUL PROCESS FOR DETERIORATION OF ANY RADIOACTIVE MATERIALS AND OR RADIATION , THAT WILL ENHANCE , IMPROVE AND PROTECT THE ENVIRONMENT; AND

TO PROVIDE A NEW AND USEFUL PROCESS FOR DETERIORATION OF RADIATION AND RADIOACTIVE MATERIALS , THAT WILL ALLOW FOR THE CLEAN-UP AND PROCESSING OF ALL RADIOACTIVE BURIAL AND WASTE DUMP SITES EXISTING TODAY ANYWHERE IN THE WORLD.

DESCRIPTION OF THE PREFERRED EMBODIMENT

IN THE FOLLOWING EXAMPLES OF THE PROCESS OF THE PRESENT INVENTION , DIFFERENT RADIOACTIVE MATERIALS AND EXAMPLES ARE USED , (80%) URANIUM OXIDE , CESIUM 137 , COBALT 60 RADIONUCLIDES AND CLOTHING CONTAMINANTED WITH RADIONUCL IDES DESCRIBED ABOVE. BOTH RADIONUCLIDES ARE NUCLEAR MEDICAL WASTES AND OTHER URANIUM AND RADIOACTIVE PARTICLE MATTER.

THE SOLID MATERIAL OR ASH PRODUCTS MUST BE CONVERTED INTO A SOLUTION OR WASTE EFFLUENT 3EF0RE ANY TREATMENT OR PROCESSING CAN BEGIN. THE DIGESTION OR CONVERSION HAS ABSOLUTELY NO AFFECT ON THE REDUCTION OR DETERIORATION OF THE RADIATION OR RADIOACTIVE WASTE MATERIAL OR THE PROCESSING THEREOF, FOR THE PURPOSES OF THE PROCESS AND METHODS OF THE PRESENT INVENTION WILL ELIMINATE BURIA AND ALL WASTE SITES , TO PROTECT THE FUTURE OF OUR ENVIRNOMENT. EXAMPLE NO. 1.

FOR A ONE/TENTH OUNCE QUANTITY OF URANIUM , 2,000 MLS OF CONCENTRATED SULFURIC ACID IS ADDED TO THE URANIUM MATERIAL , NO FURTHER PROCESSING IS REQUIRED AT THIS POINT , UNDER INJECTION OF PRESSURE OF 10 TO 25 PSI , INJECT 5,000 MLS OF " SODIUM HYPOCHLOR ITE " , INTO THE RADIOACTIVE SOLUTION/EFFLUENT , RESULTING IN THE REDUCTION AND DETEROIRATION OF THE RADIATION AND WASTE MATERIALS, THE SAME PROCESS AS DESCRIBED IN EXAMPLE NO.8 AND NO.9 , WAS REPEATED WITH THE SAME RESULTS , WHICH WILL PROVIDE CONTAINMENT AND TREATMENT OF RADIATION FROM WITHIN ANY RADIOACTIVE MATERIALS, FROM WITHIN ANY NUCLEAR EXPLOSION AND OR NUCLEAR POWER PLANT EXPLOSION. THE SAME EXAMPLES WAS REPEATED WITH LOW-LEVEL WASTE ASH'S FROM AN INCINERATOR TEST UNIT, THE CLOTHING MATERIALS WERE CONTAMINANTED WITH RADIONUCLIDES SUCH AS CESIUM 137 AND COBALT 60 WHICH WAS MEDICAL WASTES , THIS METHOD AND PROCESS WILL ELIMINATE THE NEED FOR ANY BURIAL OR WASTE DUMP SITES ANYWHERE IN THE WORLD OTHER ACIDS WILL NOT GIVE THE SAME END RESULTS OR MEET THE CHEMIC REQUIREMENTS AND ENERGY LEVEL'S REQUIRED IN THE PROCESS AND TREAT MENT LEVELS OF THE ENERGY REQUIRED. AFTER THE URAN I UM/WASTE COMPPOUND ARE DIGESTED BY THE SULFURIC ACID , WHICH IS STILL RADIOACTIVE IN THE SOLUTION/EFFLUENT , SODIUM HYPOCHLORITE IS INJECTED INTO THE WASTE SOLUTION UNDER 10 TO 25 PSI , TO COMPLETE THE REDUCTI ON AND DETERIORATION OF THE RADIATION WITHIN THE WASTE SOLUTION/EFFLUENT. THE CHLORINE MAY BE ADDED IN ANY OF SEVERAL FORMS SOLUTION OR POWDER , BUT PREFERABLY IN THE FORM OF A CHLORINE SOLUTION , SUCH AS SODIUM HYPOCHLORITE. THE SODIUM HYPOCHLORITE FORMS INTO HYPOCHLOROUS ACID IN THE WASTE EFFLUENT SOLUTION , HYPOCHLOROUS ACID , THOUGH RELATIVELY UNSTABLE , IS A STRONG ACID SOLUTION , TO COMPLETE THE NATURE AND CHEMICAL REACTION OF THE PROCESS. THE ACIDIC SOLUTION OF THE NOW NON-RADIOACTIVE EFFLUENT , BECOMES CLEAR IN A SHORT PERIOD OF TIME. THE CLEAR EFFLUENT INDICATES THAT THE REDUCTION AND DETERIORATION OF THE RADIATION IS COMPLETE AND THEREFOR READY FOR DISPOSAL THROUGH EVAPORATION METHODS AVAILA3LE THAT WILL PROVIDE PROTECTION FOR THE ENVIRONMENT, AFTER NEUTRALIZATION WITH SODIUM CARBONATE,

RADIATION READINGS FROM A GEIGER COUNTER WHICH DETECTS ALPHA BETA AND GAMMA RADIATION , PRIOR TO THE BEGINING OF THE PROCESS WERE TAKEN ON THE 100 SCALE , AND READ ABOUT .05 , WHICH IS BELuW BACKGROUND READINGS AT THE END OF THE PROCESS, THE .05 READING ON THE 1 SCALE COMPRISES BELOW BACKGROUND RADIATION LEVELS FOR THIS AREA OF THE COUNTRY. CHEMICAL ASSAY OF THE WASTE EFFLUENT OR THE WASTE SOLUTION , THAT WILL CONFIRM COMPLETE DISPOSAL OF THE LLRW RADIATION FROM THE RADIOACTIVE MATERIALS PROCESSED. CHEMICAL ASSAY WAS ALSO CONDUCTED ON THE PROCESSING AND TREATMENT OF THE URANIUM BEFORE AND AFTER TREATMENT , ALL TESTING WAS DONE IN A OUTSIDE

INDEPENDENT RESEARCH AND CHEMICAL LABORATORY, IN THE PRESENT DAY OF THE NUCLEAR INDUSTRY WASTE MATERIALS ARE CLASSIFIED ACCORDING TO THERE CONCENTRATION OF RADAITION AND DECAYING RATE OF THERE HALF-LIFE , CLASS A, B, C WASTES AND GENERAL TRASH , AND THIS IS THE PURPOSE OF THIS INVENTION , FOR SAFE AND COMPLETE DISPOSAL OF THESE WASTE PRODUCTS, EXAMPLE NO, 2,

THE ABOVE EXAMPLE DESCRIBES THE RADIATION DETEROIRATION FROM A RELATIVELY PURE FORM OF URANIUM OXIDE AND OTHER LLRW WASTE MATERIALS. FOR THE URANIUM IN WHICH CONTAMINANTS ARE ADDED FOR ENRICHMENT PURPOSES , THE ABOVE PRIMARY CHEMICALS , THE SULFURIC ACID , THE SODIUM HYPOCHLORITE (OR CHLORINE ION PROVIDING SOLUTION) , SUCH AS SODIUM HYPOCHLORITE WILL STILL BE USED , BUT THE QUANTITIES OF SUCH AGENTS ARE INCREASED SUBSTANTIALLY OVER THOSE DESCRIBED IN THE FIRST EXAMPLE. FOR SOME LLRW AND HLRW MATERIALS WITH SUBSTANTIAL QUANTITIES OF CONTAMINANTS , MORE ACID'S WILL BE REQUIRED FOR SUBSTANTIALLY AND COMPLETELY TREATING THE CONTAMINANTS AND OTHER RADIOACTIVE MATERIALS. IN SUCH CASE'S , A STRONGER SOLUTION OF (AQUA REGIA) MUST BE USED FOR THE DIGESTION AND CONVERSION PROCESS UNDER 10 TO 25 PSI , AFTER THE MATERIAL AND THE CONTAMINATING ELEMENTS ARE

DIGESTED IN THE (AQUA REGIA) SOLUTION , THE WASTE EFFLUENT WILL CONTAIN A HIGH CONCENTRATION OF RADIATION , THE CONCENTRATED SULFURIC ACID IS THEN ADDED TO THE RADIOACTIVE MATERIALS LEFT IN THE SOLUTION , AS IN EXAMPLE NUMBER ONE. THE SULFURIC ACID IS USED TO PROVIDE THE SULFATE ION WHICH COMBINES WITH THE

URANIUM TO FORM A RADIOACTIVE SULFATE, THE RADIOACTIVE SULFATE IS A SUBSTANTIAL IMPORTANCE IN THE PROCESS OF HASTENING THE REDUCTION AND DETEROIRATI ON OF THE RADIATION WITHIN THE MATERIAL. THE CHLORINE ION , AGAIN PREFERABLY IN THE FORM OF A COMMERCIAL SODIUM HYPOCHLORITE LIQUID OR POWDER , IS ALSO ADDED , AS IN THE PREVIOUS EXAMPLE , THE RESULTING SOLUTION IS AGAIN HIGHLY ACIDIC , WITH A _PH OF 01 , THEN THE SODIUM CARBONATE IS ADDED TO NEUTRALIZE THE ACIDIC SOLUTION , WHICH PREPARES THE SOLUTION FOR COMPLETE DISPOSAL THROUGH EVAPORATION METHODS AVAILABLE. EXAMPLE NO. 3 .

A QUANTITY OF 5,000 MLS OF CONCENTRATED SULFURIC ACID IS ADDED TO ONE/TENTH OUNCE OF URANIUM OXIDE , UNDER INJECTION OF PRESSURE OF 10 TO 25 PSI , THEN INJECT 10,000 MLS OF " SODIUM HYPOCHLORITE " , TO COMPLETE THE DETERIORATION OF THE RADIATION, THE RADIATION DETERIORATES BY CHEMICAL REACTION OF THE SULFURIC AND SODIUM HYPOCHLORITE. THE SOLUTION WILL REMAIN IN ITS PRESENT FORM OF THE DISSOLVED STATE IN THE SULFURIC ACID AND SODIUM HYPOCHLORITE MIXTURE. THE PH OF THE SOLUTION IS AGAIN .01 AND LESS AT TIMES , INDICATING A STRONGLY ACIDIC SOLUTION , READY FOR NEUTRALIZATION AND THEN DISPOSAL THROUGH EVAPORATION.

URANIUM USUALLY WILL NOT FORM A GASEOUS COMPOUND. FOR EXAMPLE , THE GASEOUS COMPOUND OF URANIUM HEXAFLUORIDE IS NORMALLY MADE BY THE WELL KNOWN DIFFUSION PROCESS. THE PROCESS IS DIFFERENT EXPENSIVE AND REQUIRES ELABORATE AND SOPHISTICATED EQUIPMENT , IT HAS BEEN POSTULATED THAT URANI UM/RADON GAS MAY FORM DURING THE CHEMICAL PROCESSES DESCRIBED HEREIN AND THAT THE DETERIORATION OF THE RADIATION , IS SIMPLY A TRANSFERENCE OF THE RADIATION INTO A GAS AND AWAY FROM THE RADIOACTIVE SOLUTION OF THE CHEMICAL PROCESS, HOWEVER , SINCE NEITHER URANIUM HEXAFLUORIDE , NOR ANY OTHER KNOWN GASEOUS URANIUM COMPOUND CAN BE FORMED BY THIS PROCESS AND METHODS , THE GASEOUS FORMATION THEORY HAS BEEN DISREGARDED BY TESTING OF THE METHODS DESCRIBED HEREIN. TO CONFIRM THAT THE DECLINE AND REDUCTION OF RADIATION IS NOT BEING ACCOMPLISHED BY A GASEOUS DIFFUSION INTO THE ATMOSPHERE , A STANDARD LABORATORY FILTER AND THEN INDUSTRIAL CHEMOX FILTERS DESIGNED TO TRAP RADON GASEOUS FORMS IF IT WAS TO FORM FROM ANY DIFFUSION PROCESS. AFTER THE PROCESS WAS COMPLETED , AS OUTLINED HEREIN , THE FILTER PAPER AND THE INDUSTRIAL FILTERS AND SOLUTION WERE TESTED FOR RADIOACTIVITY WITH THE GEIGER COUNTER AND CHEMICAL ASSAY , THE RESULTS WERE AS SETFORTH , READING BELOW BACKGROUND , AND THE POSTIVE ASSAY REPORT EXAMPLE NO. 4.

5 MLS OF LIQUID CESIUM 137 WHICH WAS ALREADY IN A HYPOCHLORIC BASE SOLUTION , WAS PUT INTO THE TREATMENT CHAMBER , 250 MLS OF WATER , 500 MLS OF CONCENTRATED TOLUENE AND 1,000 MLS OF SULFURIC ACID WAS ADDED TO THE CONTAINER , 1,000 MLS OF SODIUM HYPOCHLORITE WAS INJECTED UNDER 10 TO 25 PSI , THE SAME REACTION RESULTED AS DESCRIBED IN THE OTHER FOREGOING EXAMPLES , THE CONTAINER WAS VENTED THROUGH THE FILTERING SYSTEM , AND THE SAME RESULTS WAS OBTAINED WHEN CHECKED FOR RADIATION. THE LIQUID CESIUM 137 AT THE EEGINING OF THE TEST PROCEDURE REGISTERED ABOUT 26,000 COUNTS IN A FIFTEEN-SECOND COUNTING PERIOD, AT THE END OF THE TREATMENT PROCESS DESCRIBED HEREIN , THE COUNTING PERIOD HAD FALLEN TO ZERO. AGAIN ALL FILTERS WAS ASSAYED AND NO RADIATION WAS DETECTED.

EXAMPLE NO. 5. 5 MLS OF LIQUID COBALT 60 AND 5 MLS OF LIQUID CESIUM 137 IN A

HYDROCHLORIC ACID EASE SOLUTION WERE MIXED TOGETHER , THEN 5 MLS OF THE COMBINED SOLUTION WAS PLACED IN A TREATMENT CHAMBER , 250 MLS OF WATER , 500 MLS OF TOLUENE AND 1,000 MLS OF CONCENTRATED SULFURIC ACID WERE ADDED TO THE RADIOACTIVE SOLUTION , THEN 1,000 MLS OF SODIUM HYPOCHLORITE IS INJECTED UNDER 10 TO 25 PSI INTO THE TREATMENT CHAMBER , AFTER ABOUT FIVE MINUTES FROM THE BEGINING OF THE TEST PROCEDURE , THE RADIATION TESTS RESULTED IN A ZERO COUNT. AT THE BEGINING OF THE TEST PROCEDURE , THE COMBINED SOLUTION REGISTERED ABOUT 48,000 COUNTS IN A FIFTEEN COUNTING PERIOD , AT THE END OF THE TREATMENT PROCESS THE COUNT HAD BEEN REDUCED TO

ZERO, THE TREATMENT CHAMBER WAS AGAIN CONNECTED TO THE FILTER SYSTEM DESCRIBED IN EXAMPLES No. 3 AND No. 4, , NO RADIATION WAS DETECTED IN THE FILTER SYSTEM , ACCORDING TO INSTRUMENT READINGS AND FURTHER CHEMICAL ASSAY IN THE LABORATORY, EXAMPLE NO. 6.

5 MLS OF LIQUID CESIUM 137 , ITF A HYDROCHLORIC BASE SOLUTION DILUTED WITH , 100 MLS OF WATER , TO CONVERT THE CESIUM 137 TO A CESIUM 137 HYDROXIDE , THEN AD 1,000 MLS OF CONCENTRATED SULFURIC ACID INTO THE RADIOACTIVE SOLUTION , THEN 5,000 MLS OF SODIUM

HYPOCHLORITE , UNDER INJECTION PRESSURE OF 10 TO 25 PSI INTO THE TREATMENT CHAMBER , WITHIN A MATTER OF MINUTES THE PROCESS IS THEN COMPLETE , THE REDUCTION OF THE RADIATION IS COMPLETED , THE RADIATION COUNT WAS ABOUT 26,000 , IN A FIFTEEN-SECOND COUNTING PEROID , AT THE END OF THE PROCESS THE COUNT WAS ZERO , FURTHER TESTING AND CHEMICAL ASSAY DETECTED NO RADIATION , IN THE FILTERS OR THE EFFLUENT SOLUTION , WHICH IS NOW READY FOR SAFE DISPOSAL THROUGH EVAPORATION METHODS THAT ARE NOW AVAILABLE. 2,000 MLS OF LIME WATER MAY BE USED , IN PLACE OF SODIUM CARBONATE TO CURE THE HIGHLY ACIDIC SOLUTION PH OF .01 , BEFORE THE FINAL STEP OF DISPOSAL. EACH EXAMPLE AS SETFORTH , DEMONSTRATES TOTAL REDUCTION AND

DETERIORATION OF THE RADIOACTIVE MATERIALS AS PROCESSED.

EXAMPLE NO, 7,

5 MLS OF LIQUID COBALT 60 , IN A HYDROCHLORIC BASE SOLUTION WAS PLACED INTO THE TREATMENT CHAMBER , THEN ADD 1,000 MLS OF

CONCENTRATED SULFURIC ACID , WAS ADDED TO THE RADIOACTIVE SOLUTION , THEM 5,000 MLS OF SODIUM HYPOCHLORITE , UNDER INJECTION PRESSURE OF 10 TO 25 PSI INTO THE TREATMENT CHAMBER , WITHIN A MATTER OF MINUTES THE PROCESS IS THEN COMPLETE , THE REDUCTION OF THE RADIATION IS COMPLETED , THE RADIATION COUNT WAS ABOUT 48,000 , IN A FIFTEENSECOND COUNTING PERIOD , AT THE END OF THE PROCESS THE COUNT WAS ZERO , FURTHER TESTING AND CHEMICAL ASSAY DETECTED NO RADIATION , IN THE FILTERS OR THE EFFLUENT SOLUTION , WHICH IS NOW READY FOR SAFE DISPOSAL THROUGH EVAPORATION METHODS THAT ARE NOW AVAILABLE , AFTER TREATMENT OF THE PH .01 , IS TREATED. EXAMPLE NO. 8,

IN REGARD TO ADDITIONAL APPLICATIONS AND USE OF THE PROCESS AND METHODS DESCRIBED IN THE FOREGOING EXAMPLES , IN THE CASE OF NUCLEAR EXPLOSION OF ANY NATURE , THE APPLICATION OF THE FOREGOING METHODS MAY BE APPLIED , ONLY A DIFFERENT PROCEDURE IS USED IN THE SAFE TREATMENT AND DISPOSAL OF THE RADIOACTIVE MATERIALS WITHIN THE RADIOACTIVE ZONE ABOVE THE EXPLOSION SITE OR ZONE , RAPID AIR BORNE AIRCRAFT , WILL BE ABLE TO CONTAIN THE FALL-OUT WITHIN THE RADIOACTIVE ZONE BY RELEASING THE PROPER MIXTURE OF CHEMICALS , CONCENTRATED SULFRURIC ACID AND SODIUM HYPOCHLORITE , UNDER PRESSURE OF 50 PSI INTO RADIOACTIVE ZONE , TREATMENT WILL CONTAIN ANY AND ALL RADIATION AND RADIOACTIVE FALL-OUT , WITHIN THE EXPLOSION ZONE OR AREA, THE RADIATION AND RADIOACTIVE MATERIAL WITHIN THE RADIOACTIVE CLOUD OVER THE EXPLOSION ZONE WILL NOT ESCAPE FROM THE AREA OR TREATMENT ZONE OF THE CHEMICAL TREATMENT FOR THE CONTAINMENT AND COMPLETE DISPOSAL , THAT WILL SAVE THE ENVIRONMENT FROM SUCH A NUCLEAR POWER PLANT EXPLOSION OR OTHER TYPE OF NUCLEAR EXPLOSION, THIS PROCESS AND METHODS OF APPLICATIONS WILL CONTAIN THE RADIOLOGICAL CONSEQUENCES OF ANY TYPE NUCLEAR EXPLOSION , FROM A NUCLEAR POWER PLANT FAILURE OR OTHER SOURCE OF NUCLEAR EXPLOSION ANYWHERE IN THE WORLD,

EXAMPLE NO. 9.

THE RADIOACTIVE SAMPLE OF (80%) URANIUM WAS IN A DRY POWDER TO REPRESENT RADIATION AND RADIOACTIVE PARTICLE FALL-OUT OF AND WITHIN A NUCLEAR EXPLOSION OF ANY NATURE, THE DRY RADIOACTIVE

POWDER WAS ENJECTED INTO A GLASS CONTAINER UNDER AIR PRESSURE OF 5 TO 10 PSI , TO GENERATE A MISTY CLOUD OF RADIOACTIVE MATERIAL , WITHIN THE AIR CHAMBER, THEN SULFURIC ACID AMD SODIUM HYPOCHLORITE WAS INJECTED INTO THE TREATMENT CHAMBER OF RADIOACTIVE MATERIAL UNDER 10 TO 25 PSI, THE RADIOACTIVE MATERIAL WITHIN THE CHAMBER AS A RADIATION SIMULATED RADIOACTIVE CLOUD , BEGAN TO LOSE ITS ENERGY AND LOSS OF RADIATION ACCORDING TO THE INSTRUTMENT READINGS, WITHIN A VERY SHORT PERIOD OF TIME THE RADIATION AND THE RADIOACTIVE CLOUD CLEARED UP , NO TRACE OF THE (80%) URANIUM OR RADIATION COULD BE SEEN OR FOUND WITHIN THE AIR CHAMBER , NO TRACES OF ANY RADIATION COULD BE FOUND WITHIN THE TEST CHAMBER. OTHER TESTS OF THIS DESCRIPTION WAS MADE WITHIN A (55) GALLON DRUMS , WITH THE SAME END RESULTS. OTHER TESTS CONSISTED OF LIQUID SPRAY MATERIALS SUCH AS CESIUM 137 , COBALT 60 , AND AIRBORNE ASH'S CONTAMINATED WITH OTHER RADIONUCLIDES AND OTHER HLRW MATERIALS NOT DISCLOSED IN THE SUBJECT MATTER , BECAUSE OF POSSIBLE NATIONAL SECURITY MATTERS MAY BE INVOLVED OR POSSIBLE DEFENSE APPLICATIONS,

Claims

WHAT IS CLAIMED IS :

1, THE PROCESS FOR THE REDUCTION AND DETERIORATION OF HARMFUL RADIATION FROM RADIOACTIVE MATERIAL FOR COMPLETE AND SAFE DISPOSAL , TO PROTECT THE ENVIRONMENT , THEREOF COMPRISING STEPS OF :

ADDING A FIRST QUANTITY OF ACID SOLUTION TO THE RADIOACTIVE MATERIAL TO BEGIN DIGESTING THE RADIOACTIVE MATERIAL ; AND ADDING

A SECOND QUANTITY OF SODIUM HYPOCHLORITE TO THE FIRST QUANTITY OF THE ACID SOLUTION TO PROVIDE HYPOCHLOROUS ACID TO COMPLETE THE REDUCTION AND DETERIORATION OF THE RADIOACTIVE MATERIAL AND THE HARMFUL RADIATION FROM WITHIN THE RADIOACTIVE MATERIALS , SUCH URANIUM , MEDICAL RADIONUCLIDES , AND RADIOACTIVE MATERIAL AND RADIATION WITHIN ANY NUCLEAR EXPLOSION,

2, THE PROCESS OF CLAIM 1 IN WHICH THE ACID SOLUTION COMPRISES CONCENTRATED SULFURIC ACID FOR BEGINING THE TREATMENT OF THE RADIOACTIVE MATERIALS , SOLID AND LIQUID,

3, THE PROCESS OF CLAIM 2 WHICH FURTHER INCLUDES THE STEP OF NEUTRALIZING THE ACID SOLUTION OF SULFURIC ACID , SODIUM HYPOCHLORITE AND NOW NON-RADIOACTIVE SOLUTION , READY FOR A SAFE AND COMPLETE DISPOSAL.

4, THE PROCESS OF CLAIM 3 IN WHICH THE STEP OF NEUTRALIZING THE NON-RADIOACTIVE SOLUTION COMPRISES ADDING A QUANTITY

OF SODIUM CARBONATE TO REDUCE THE .01 PH DOWN TO 7 , FOR COMPLETE AND SAFE DISPOSAL , THAT WILL ELIMINATE THE NEED FOR ANY BURIAL OR WASTE DUMP SITES ANYWHERE IN THE WORLDD

5, THE PROCESS OF CLAIM 3 WHICH INCLUDES THE STEP OF PROVIDING A METHOD FOR NON-RADIOACTIVE MATERIALS AND SOLUTIONS SAFE DISPOSAL THAT WILL PROTECT THE ENVIRONMENT, 6, THE PROCESS OF CLAIM 1 IN WHICH THE RADIOACTIVE WASTE PRODUCTS AND THE ACID SOLUTIONS INCLUDE AQUA REGIA FOR DIGESTING THE CONTAMINANTS AND THE RADIOACTIVE WASTE PRODUCTS PREPARING THEM FOR ADDITIONAL TREATMENT.

7, THE PROCESS OF A SAFE AND COMPLETE DISPOSAL FOR ALL LOW-LEVEL RADIOACTIVE MATERIALS AND RADIATION AS CLAIMED IN CLAIM 1 WHEREIN THE RADIATION DISPOSAL BY ACID SOLUTIONS WITHIN THE CHEMICAL REACTIONS COMPLETE THE DISPOSAL,

8, THE PROCESS OF CONTAINMENT WITH COMPLETE AND SAFE DISPOSAL FOR ALL HIGH-LEVEL RADIOACTIVE MATERIALS AS CLAIMED IN CLAIM 1 WHEREIN THE RADIATION DISPOSAL BY ACID SOLUTIONS AND OTHER CHEMICALS WITHIN THE CHEMICAL REACTIONS OF THE RADIATION,

9, THE PROCESS OF CLAIM 1 WHICH FURTHER INCLUDES COMPLETE AND SAFE DISPOSAL FOR ALL LOW-LEVEL RADIOACTIVE MATERIALS THAT WILL ELIMINATE THE NEED FOR ANY BURIAL SITES OR WASTE DUMPS WHEREIN THE RADIATION IS DISPOSED OF WITHIN THE CHEMICAL ENERGY WITHIN THE RADIATION AND CHEMICAL REACTIONS,

10, THE PROCESS OF CLAIM 1 WHICH FURTHER INCLUDES AND SAFE CONTAINMENT WITH COMPLETE DISPOSAL TREATMENT FOR ALL RADIATION FROM ANY TYPE RADIATION ANY TYPE NUCLEAR EXPLOSION WHEREIN THE RADIATION IS DISPOSED OF WITHIN THE CHEMICAL REACTIONS,