Solution of the neutron spectrum adjustment problem in a typical MTR type research reactor

Annals of Nuclear Energy

Volumn 28, Issue 1, 2001, Pages 25-51

  Malkawi, S R ^a   Ahmad, N ^a  

^a PAKISTAN INSTITUTE OF ENGINEERING AND APPLIED SCIENCES   (Pakistan)

Author keywords

[No Author keywords available]

Indexed keywords

ALGORITHMS; CODES (SYMBOLS); LIGHT WATER REACTORS; MATERIALS TESTING; NUCLEAR FUELS; RESEARCH REACTORS; URANIUM;

ADJUSTMENT CODES; MATERIAL TEST REACTOR; NEUTRON ENERGY SPECTRUM ADJUSTMENT PROBLEM;

NEUTRON EMISSION;

EID: 0342484421     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0306-4549(00)00021-9     Document Type: Article

References (25)

1. Baard, J.H., Zijp, W.L., 1981. Nuclear Data Guide for Reactor Neutron Metrology. EUR 7164 EN. Commission of the European Communities.
2. Bondars, H.Y., 1988. Definition of the Problem of Neutron Spectra Unfolding by Measured Reaction Rates. Report IAEA-TECDOC-469.
3. Browne, E., Firestone, R.B., 1986. Table of Radioactive Isotopes. John Wiley & Sons.
4. Debertin, K., Helmer, R.G., 1988. Gamma- and X-ray Spectrometry with Semiconductor Detectors. North-Holland.
5. Fowler, T.B., Vondy, D.R., Cunningham, G.W., 1971. Nuclear Reactor Core Analysis Code CITATION. ORNL-TM-2496 Rev. 2.
6. Griffin, P.J., Kelly, J.G., Luera, T.F., 1992. Effect of New Cross Section Evaluations on Neutron Spectrum Determination. SAND-92-0093C. Sandia National Laboratories.
7. Halsall, M.J., 1980. Summary of WIMSD-4 Input Options. AEEW-M 1327.
8. Iqbal M. Comparison of experimental and calculated neutron spectra for Pakistan research reactor-1. Nuclear Science Journal. 32:1995;365-375.
9. Iqbal M., Ansari S., Zafar M. A comparison of neutron energy spectra in low-enriched and high-enriched uranium cores. J. Neutron Research. 3:1996;273-283.
10. Itoh S., Tsunoda T. Neutron spectra unfolding with maximum entropy and maximum likelihood. Journal of Nuclear Science and Technology. 26(9):1989;833-843.
11. Khan, L. A., Israr, M., Arshad, M., Karim, A., Akhtar, K. and Moquit, A., 1992. Pakistan Research Reactor-1 Final Safety Analysis Report for Conversion to LEU Fuel and Power Upgradation, Revision-1.
12. Knoll, G. F., 1989. Radiation Detection and Measurement. John Wiley & Sons.
13. Kocherov, N.P., 1996. Neutron Metrology File NMF-90, INDC (NDS)-347.
14. Krane, K.S., 1988. Introductory Nuclear Physics. John Wiley & Sons.
15. Malkawi S.R., Ahmad N. Prediction and measurement of neutron energy spectrum in a material test research reactor. Annals of Nuclear Energy. 27:2000;311-327.
16. Matzke, M., 1994. MIEKE. A Package of Programs for Neutron Spectrum Adjustment based on Few Channel Measurements. README text in the program package. Physikallische-Technische Bundesanstalt.
17. McElory, W.N., Berg, S., Crockett, T., Hawkins, R.G., 1967. A Computer Automated Iteration Method for Neutron Flux Spectra Determination. Report AFWL-TR-67-41, Vols. I-IV. Air Force Weapons Laboratory, New Mexico.
18. Nolthenius, H. J., 1981. A Program for the Conversion of Fine Group Flux Density and Cross-section Data to Coarse Group Values. Report ECN-92. ECN Petten.
19. Nolthenius, H.J., 1988, Information for the REAL-88 Exercise. Report ECN-88-023.
20. Perry, F.G, 1977. Least Square Dosimetry Unfolding: The Program STAY'SL. Report ORNL/TM-6062, ENDF-254. ORNL.
21. Szondi, E.J., Zsolnay, E.M., 1992. Documentation of the Code SANDBP. Institute of Nuclear Technical University of Budapest.
22. Zijp, W.L., 1984. Lecture Notes on Computerised Neutron Spectrometry. Report ECN-153.
23. Zijp, W.L., Zsolnay, E.M., Nolthenius, H.J., Szondi, E.J., Verhang, G.C.H.M., Cullen, D.E., Ertek, C., 1983. Report ECN-128. Final Report on the REAL-80 Exercise.
24. Zijp, W.L., Zsolnay, E.M., Nolthenius, H.J., Szondi, E.J., 1988. Report ECN-212. Final Report on the REAL-84 Exercise.
25. Zsolnay, E.M., Nolthenius, H.J., Greenwood, L.R., Szondi, E.J., 1990. Report PNL-SA-18648. Reference Data File for Neutron Spectrum Adjustment and Related Radiation Damage Calculations.