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%,*.... DEC 181978 p.pr MEMORANDUM FOR: Thomas E. Murley, Director Division of Reactor Safety Research FROM: L. S. Tong, Assistant Director for Water Reactor Safety Research
SUBJECT:
TRIP REPORT TO TAIWAN AND JAERI I
A. Visit to Taiwan, ROC (December 4 to 10, 1978)
! 1. Lectures on the status of NRC water reactor safety research were delivered at the Institute of Nuclear Energy Research (INER) and Taiwan Power Company, respectively. Both organizations showed interest in water reactor safety research and requested invitations to attend the next NRC water reactor safety informa-l tion meeting.
- 2. Dr. Ji-Peng Chien requested NRC research infomation regarding non-destructive examination and noise analysis. I suggested that he direct such a request to Dr. J. Lafleur of IP.
- 3. The reactor site at Chinsan was visited. One 600 MW-BWR is in operation. Another 600 MW-BWR will be in operation in early 1979.
Two 1000 MW-BWR are under construction and planned to be operational in 1980. The management and control of the work seems excellent.
They are kept well infomed on U.S. reactor operating problems and safety information.
- 4. I handed out copies of the LOFT Executive Summary and two published papers:
"NRC Water-Reactor Safety-Research Program," Nuclear Safety, Vol. 18, No. 1. February 1977.
" Heat Transfer in Reactor Safety," ASME-AICHE 6th International Heat Transfer Conference, Toronto, August 1978.
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Thomas E. Murley DEC 181978 B. Visit to JAERI. Tokai. Japan (December 11-14,1978)
- 1. All water reactor safety research facilities at JAERI were visited. Their research results and current status were dis -
cussed in detail. A summary of JAERI's five-year plan for safety research is shown in Enclosure 1 and the annual budget for Japanese water reactor safety research is listed in Enclosure 2.
- 2. The 3-D Cylindrical Core Test Facility construction is completed and ready for Japanese government acceptance check on December 20th.
Shakedown tests are planned to be completed in March, 1979. The next 20/3D Technical Coordination Comittee Meeting is suggested being held in Japan in April 1-4, 1979.
- 3. 2-1) slab core design was reviewed and the instrumentation plan suggested by NRC was accepted by JAERI with mutually agreed upon modifications.
- 4. The Pipe-Whip test facility is very impressive. Test data on i a 4" elbow and straight pipe have been given to the writer, and will be analyzed by Mr. C. Serpan's branch. JAERI is planning to test 8" diameter pipes next year. These results could be used for our needs, h 5. A full-scale, 20 0sector BWR R II containment test facility is near completion. Tests are planned to start in early 1979.
- 6. Fuel rod failure studies are emphasized at JAERI. Currently in NSRR, over one hundred tests have been conducted. A large hot-cell has been built for examination of full size PWR fuel assemblies, including fuel rod cutting and metallugraphic examinations.
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- 7. Varies ways of thennocouple attachment onto electric heaters and nuclear fuel rods were tested and data were compared. The surface-buried ttie~nnocouples give the most accurate measurement, m
- 8. During his visit, the writer received excellent technical cooperation,and hospitality as stated.
$ 5'. W P L. S. Tong, Assistagt Director for Water Reactor Safety Research
Enclosures:
As stated cc: See next page l
Thomas E. Murley DEC 181978 cc: S. Levine J. Lafleur R. Budnitz A. Spano S. Hanauer R. Tedesco WRSR Branch Chiefs and Section Leaders e
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ENCLOSURE 1 JAERI PLANS FOR SAFETY RESEARCH RESEARCH TOPICS 1977 1978
- 1. NUCLEAR FUEL SAFETY 1979 1980 1981
- Fuel element behavior under irradiation
- Development of computer code for evaluation of fuel Irradiation test of JMIR, HALDEN RBWB. and STUDSVIK R2 element safety
- Behavior of in-reactor release of FP Development of analytical code for fuel behavior under normal and
- Tests for LWR fuel material integrity Analysis of irradiation tests at JMTR and NSRR
' Construction of practicalEx-core experiment and analysis of F8F data
- 2. INTEGRITY OF REACTOR PRESSURE BOUNDARY post irradiation testing of
- Reactor structural materials l
- Tests for coolant piping reliability Irradiation embrittlement testing of structural steel and testing l
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- Testing of pump operability during earthquake ry testsof Manufacture of test equipsent, crack propsgation behavior based on rupture mechan prelimina
- Safety under missile loads Seismic testing of pimps and analyses i
! Investigation of missile loads and analy ses
- 3. TESTINC OF ENGINEERED OF COOLANT ACCIDENT SAFETY FEATURES FOR IASS
- ECCS tests at ROSA
- LOFT experiments Analyses of ROSA-II PWR simulation tests
- Fuel element behavior during reflood Analyses of ROSA-!!! BWR simulation tests Analyses of LOFT test data I
- Fuel cladding behavior during accident Construction of LSRT facility I
- Reliability of containment pressure suppression system Demonstration tests l Design and construction of pressure suppression 21rcaloy-water reactio
- Effectiveness of containment spray syst m test facility Demonstration tests i
themal char- Iodine removal demonstration i
acteristics Analyses
, tests i
4._ REACTIVITY ACCIDENT tests
- Testing at NSRR Water capsule and loop experiments for fuel damage
- 5. _ ANALYTICAL EVALUATION OF REACTOR SAFETY Water /Na capsule and loop experiments
- Development of computer coces for LWR safety y'
Evaluation of LVR safety Development of LOCA-ECCS evaluation code system and development of various I accident evaluation codes
- Safety evaluation of nuclear fuel facilities Analytical evaluation of actual reactor safety and evaluation and improvement of code capability
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- Development of reactor safetyof methodology for probabilistic evaluation Complition of evaluation code system
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Preliminary inesstigation Development of methodology
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ANALYSIS AND EVALUATION OF ENVIRONMENTAL RADIOACTIVITY .
- Evaluation of environmental radiation measurements Evaluation of Y-rsy
- Development of Y-ray Analyses of Y-ray characteristics discrimination Evaluation of measurements of radionuclides in measurement
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Environmental behaviors Investigation of detailed distribeHea ae I
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- 6. ANALYSIS AND EVALUATION OF ENVIRONNENTAL RADIOACTIVITY J
- Evaluation of environmental radiation measurements Evaluation of Y-ray Development of Y-ray t
Analyses of Y-ray characterirties discrimination measurement I
- Evaluation of messijraments of radionuclides in Environmental behaviors environment Investigation of detailed distribution of of sg, nog, 2"Pu background radiation
- Diffusion model for gaseous and liquid wastes Analyses of diffusion Development of 2-layer " sea-wind" Development of
- Development of evaluation system for environmental parameters diffusion model diffusion mod.t1 radioactivity Development of evaluation code for nomal and credible accident doses
- 7. RADIOACTIVE WASTE MANACEMENT
- Safety evaluation tests for solidified low-level wastes Imach and swelling tests of cement and asphalt solidified products Multi-barrier
! package teach j
- Safety evaluation tests for solidified intermediat'e-level Asphalt and plastic solidification tests, plastic solidification demonstration testa
! wastes tests and package safety tests
- Safety evaluation tests for solidified high-level wastes Enclosure tests and tests for characterization of enclosed
), solidified product
- Safety of geological disposal of high-level wastes Survey Thermal characteristics of rocks and nuclides
- Development of new technology for high-level waste movement measurements i' management Ceramic solidification, metallic solidification, glass-ceramics, and quantitative
! evaluation code development
- Construction of safety testing facility for wastes Design and construction Installation of equipment Test 1
- Corrosion safety tests for radioactive waste containers Facility construction operation j
- Ocean disposal of radioactive wastes Demonstration tests j Preparation for integrity tests of experimental Test disposal and evalu.ation i
- Safety of land disposal of radioactive wastes deep-sea disposal container 1 Basic research for ground Facility survey Esvironment simulation teste movement of nuclides and construction
) 8. ENVIROl9fENTAL SAFETY REIATED RESEARCH i
- Basic research on tritium release iodine from irradiated fuel natural environment Release behavior from irradiated fuel, loop release experiments;
- Isolation, concentration, and solidification of Krypton concentration, storage, synthesis of krypton fluoride.
krypton and solidification Evaluation
- Removal of volatile FP from reprocessing stream Tritim removal and basic research on of f-gas
- Partition and transmutation of FP nuclides Development of final disposal technology
- Development of radiation technology for conservation of Development of technology for of f-gas disposal and environment waste water disposal
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ENCLOSURE 2 3 ANNUAL BUDGET for WATER REACTOR SAFETY RESEARCH of JAPAN
$ 10' YEARS JAERI NPETC* TOTAL 1974 18.6 0 18.6 1975 32.7 6.4 39.1 1976 45.4 24.7 70.1 1977 50.7 30.0 80.7 l 1978 56.6 30.8 87.4 1979 52.6 34.2 86.8 i
- The Nuclear Power Engineering Tect Center l
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