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JAEA Reports

Calculations of Tritium Recoil Release from Li and U Impurities in Neutron Reflectors (Joint research)

Ishitsuka, Etsuo; Kenzhina, I.*; Okumura, Keisuke; Ho, H. Q.; Takemoto, Noriyuki; Chikhray, Y.*

JAEA-Technology 2018-010, 33 Pages, 2018/11

JAEA-Technology-2018-010.pdf:2.58MB

As a part of study on the mechanism of tritium release to the primary coolant in research and testing reactors, tritium recoil release rate from Li and U impurities in the neutron reflector made by beryllium, aluminum and graphite were calculated by PHITS code. On the other hand, the tritium production from Li and U impurities in beryllium neutron reflectors for JMTR and JRR-3M were calculated by MCNP6 and ORIGEN2 code. By using both results, the amount of recoiled tritium from beryllium neutron reflectors were estimated. It is clear that the amount of recoiled tritium from Li and U impurities in beryllium neutron reflectors are negligible, and 2 and 5 orders smaller than that from beryllium itself, respectively.

Journal Articles

Validation of decay heat evaluation method based on FPGS cord for fast reactor spent MOX fuels

Usami, Shin; Kishimoto, Yasufumi; Taninaka, Hiroshi; Maeda, Shigetaka

Proceedings of International Conference on the Physics of Reactors; Unifying Theory and Experiments in the 21st Century (PHYSOR 2016) (USB Flash Drive), p.3263 - 3274, 2016/05

The present paper describes the validation of the new decay heat evaluation method using FPGS90 code with both the updated nuclear data library and the rational extent of uncertainty, by comparing the results of the decay heat measurement of the spent fuel subassemblies in Joyo MK-II core and by comparing with the calculation results of ORIGEN2.2 code. The calculated values of decay heat (C) by FPGS90 based on the JENDL-4.0 library were coincident with the measured ones (E) within the calculation uncertainties, and the C/E ranged from 1.01 to 0.93. FPGS90 evaluated the decay heat almost 3% larger than ORIGEN2.2, and it improved the C/E in comparison with the ORIGEN2.2 code. Furthermore, The C/E by FPGS90 based on the JENDL-4.0 library was improved than that based on the JENDL-3.2 library, and the contribution of the revision of reaction cross section library to the improvement was dominant rather than that of the decay data and fission yield data libraries.

JAEA Reports

SWAT4.0; The Integrated burnup code system driving continuous energy Monte Carlo codes MVP, MCNP and deterministic calculation code SRAC

Kashima, Takao; Suyama, Kenya; Takada, Tomoyuki*

JAEA-Data/Code 2014-028, 152 Pages, 2015/03

JAEA-Data-Code-2014-028.pdf:13.39MB

There have been two versions of SWAT depending on details of its development history: the revised SWAT that uses the deterministic calculation code SRAC as a neutron transportation solver, and the SWAT3.1 that uses the continuous energy Monte Carlo code MVP or MCNP5 for the same purpose. It takes several hours, however, to execute one calculation by the continuous energy Monte Carlo code even on the super computer of the Japan Atomic Energy Agency. Moreover, two-dimensional burnup calculation is not practical using the revised SWAT because it has problems on production of effective cross section data and applying them to arbitrary fuel geometry when a calculation model has multiple burnup zones. Therefore, SWAT4.0 has been developed by adding, to SWAT3.1, a function to utilize the deterministic code SARC2006, which has shorter calculation time, as an outer module of neutron transportation solver for burnup calculation. SWAT4.0 has been enabled to execute two-dimensional burnup calculation by providing an input data template of SRAC2006 to SWAT4.0 input data, and updating atomic number densities of burnup zones in each burnup step. This report describes outline, input data instruction, and examples of calculations of SWAT4.0.

JAEA Reports

A Set of ORIGEN2 cross section libraries based on JENDL-3.3 library; ORLIBJ33

Katakura, Junichi; Kataoka, Masaharu*; Suyama, Kenya; Jin, Tomoyuki*; Oki, Shigeo*

JAERI-Data/Code 2004-015, 115 Pages, 2004/11

JAERI-Data-Code-2004-015.pdf:16.52MB

A set of cross section libraries for ORIGEN2 code, ORLIBJ33, has been produced based on the latest Japanese Evaluated Nuclear Data Library JENDL-3.3. The produced libraries are for LWR's which include PWR, BWR and their MOX fuels. The libraries for FBR's are also produced. Using the libraries for LWR, comparisons with old libraries based on JENDL-3.2 were performed. The comparisons with measured PIE data were also carried out. For the libraries for FBR, the comparisons with the calculations using the old libraries were performed and the effects using different libraries were discussed.

Journal Articles

Validation of integrated burnup code system SWAT2 by the analyses of isotopic composition of spent nuclear fuel

Suyama, Kenya; Mochizuki, Hiroki*; Okuno, Hiroshi; Miyoshi, Yoshinori

Proceedings of International Conference on Physics of Fuel Cycles and Advanced Nuclear Systems; Global Developments (PHYSOR 2004) (CD-ROM), 10 Pages, 2004/04

This paper provides validation results of SWAT2, the revised version of SWAT, which is a code system combining point burnup code ORIGEN2 and continuous energy Monte Carlo code MVP, by the analysis of post irradiation examinations (PIEs). Some isotopes show differences of calculation results between SWAT and SWAT2. However, generally, the differences are smaller than the error of PIE analysis that was reported in previous SWAT validation activity, and improved results are obtained for several important fission product nuclides. This study also includes comparison between an assembly and a single pin cell geometry models.

JAEA Reports

Derivation of correction factor to be applied for calculated results of BWR fuel isotopic composition by ORIGEN2.1 code

Nomura, Yasushi; Mochizuki, Hiroki*

JAERI-Tech 2002-068, 131 Pages, 2002/11

JAERI-Tech-2002-068.pdf:5.59MB

no abstracts in English

JAEA Reports

Photon and decay data libraries for ORIGEN2 code based on JENDL FP decay data file 2000

Katakura, Junichi; Yanagisawa, Hiroshi

JAERI-Data/Code 2002-021, 81 Pages, 2002/11

JAERI-Data-Code-2002-021.pdf:3.62MB

no abstracts in English

Journal Articles

Determination of $$gamma$$-ray exposure rate from short-lived fission products under criticality accident conditions

Yanagisawa, Hiroshi; Ono, Akio; Aizawa, Eiju

Journal of Nuclear Science and Technology, 39(5), p.499 - 505, 2002/05

 Times Cited Count:4 Percentile:67.67(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Derivation of correction factor to be applied for calculated results of PWR fuel isotopic composition by ORIGEN2 code

Suyama, Kenya; Murazaki, Minoru*; Mochizuki, Hiroki*; Nomura, Yasushi

JAERI-Tech 2001-074, 119 Pages, 2001/11

JAERI-Tech-2001-074.pdf:4.21MB

no abstracts in English

JAEA Reports

Evaluation of burnup characteristics and energy deposition during NSRR pulse irradiation tests on irradiated BWR fuels

Nakamura, Takehiko; Takahashi, Masato*; Yoshinaga, Makio

JAERI-Research 2000-048, 77 Pages, 2000/11

JAERI-Research-2000-048.pdf:6.04MB

no abstracts in English

JAEA Reports

ORIGEN2 libraries based on JENDL-3.2 for LWR-MOX Fuels

Suyama, Kenya; Onoue, Masaaki*; Matsumoto, Hideki*; Sasahara, Akihiro*; Katakura, Junichi

JAERI-Data/Code 2000-036, 35 Pages, 2000/11

JAERI-Data-Code-2000-036.pdf:1.19MB

no abstracts in English

JAEA Reports

Revised SWAT; The Integrated burnup calculation code system

Suyama, Kenya; Kiyosumi, Takehide*; Mochizuki, Hiroki*

JAERI-Data/Code 2000-027, 88 Pages, 2000/07

JAERI-Data-Code-2000-027.pdf:4.08MB

no abstracts in English

Journal Articles

ORLIBJ32: The Set of new libraries of ORIGEN2 code based on JENDL-3.2

Suyama, Kenya; Katakura, Junichi; Okawachi, Yasushi*; Ishikawa, Makoto*

Proceedings of the ANS International Topical Meeting on Advances in Reactor Physics and Mathematics and Computation into the Next Millennium (PHYSOR2000) (CD-ROM), p.20 - 0, 2000/00

no abstracts in English

JAEA Reports

Burnup calculation with estimated neutron spectrum of JMTR irradiation field; Development of the burnup calculation method for fuel pre-irradiated in the JMTR

Okonogi, Kazunari*; Nakamura, Takehiko; Yoshinaga, Makio; *

JAERI-Data/Code 99-018, 112 Pages, 1999/03

JAERI-Data-Code-99-018.pdf:4.48MB

no abstracts in English

JAEA Reports

Libraries based on JENDL-3.2 for ORIGEN2 code; ORLIBJ32

Suyama, Kenya; Katakura, Junichi; Okawachi, Yasushi*; Ishikawa, Makoto*

JAERI-Data/Code 99-003, 83 Pages, 1999/02

JAERI-Data-Code-99-003.pdf:3.47MB

no abstracts in English

Journal Articles

Validation of SWAT for burnup credit problems by analysis of pie of 17$$times$$17 PWR fuel assembly

Suyama, Kenya; Nakahara, Yoshinori; Kaneko, Toshiyuki*;

Proc. of PATRAM'98, 1, p.239 - 244, 1998/00

no abstracts in English

JAEA Reports

Integrated burnup calculation code system SWAT

Suyama, Kenya; *; *

JAERI-Data/Code 97-047, 128 Pages, 1997/11

JAERI-Data-Code-97-047.pdf:3.06MB

no abstracts in English

JAEA Reports

A Study of burnup analysis method for irradiation test of rock-like plutonium fuel sample performed at JRR-3

Nakano, Yoshihiro; Takano, Hideki; Akie, Hiroshi

JAERI-Research 97-051, 31 Pages, 1997/07

JAERI-Research-97-051.pdf:2.41MB

no abstracts in English

Journal Articles

Decay and fission yield data library for ORIGEN2 code to reproduce the decay heat values recommended by Atomic Energy Society of Japan

Katakura, Junichi

Nippon Genshiryoku Gakkai-Shi, 38(7), p.609 - 615, 1996/00

 Times Cited Count:1 Percentile:84.64(Nuclear Science & Technology)

no abstracts in English

26 (Records 1-20 displayed on this page)