JENDL-5 benchmarking for fission reactor applications

Figures & data

Table 1. Benchmark list for the benchmark test in the ICSBEP handbook for the validation of JENDL-5.

Name	No.	Name	No.	Name	No.	Name	No.	Name	No.
HCI003	7	HST013	4	LCT030	2	PMF006	1	UMF006	1
HMF001	1	HST032	1	LCT033	6	PMF008	1	USI001	30
HMF004	1	HST042	8	LCT035	3	PMF011	1	USM001	3
HMF015	1	HST050	11	LCT048	5	PST001	6	USM002	5
HMF016	2	ICT002	6	LCT064	1	PST002	7	UST001	5
HMF028	1	IMF007	1	LCT079	10	PST003	8	UST002	17
HMF065	1	LCT001	8	LCT080	11	PST004	13	UST003	10
HMI001	1	LCT002	5	LMT001	1	PST007	8	UST004	8
HMI006	3	LCT003	23	LMT006	3	PST008	29	UST005	2
HMT001	1	LCT005	16	LMT007	6	PST009	6	UST008	1
HMT003	7	LCT006	18	LST020	4	PST011	5	UST009	4
HMT006	23	LCT007	10	LST021	4	PST018	7	UST012	8
HNT008	1	LCT008	5	MCT001	4	PST012	23	UST013	21
HMT009	1	LCT009	27	MCT002	6	PST018	9	UST015	26
HMT010	2	LCT010	30	MCT003	6	PST021	6	UST017	7
HMT012	1	LCT011	15	MCT004	11	PST022	17	Total	770
HMT013	2	LCT017	29	MCT005	7	PST028	15
HMT014	1	LCT018	1	MCT006	6	UCT001	8
HMT016	1	LCT019	3	MCT007	5	UCT004	1
HMT018	1	LCT022	7	MCT008	6	UMF001	1
HMT031	1	LCT024	2	MCT009	6	UMF002	2
HMT033	1	LCT025	4	MCT011	6	UMF003	2
HST002	14	LCT026	4	PMF001	1	UMF004	2
HST010	4	LCT027	4	PMF002	1	UMF005	2

Table 2. Parent and daughter nuclide to be analyzed for the validation of capture cross sections.

Validation	Sample	Parent nuclide	Daughter nuclide
^237Np capture	PFR ^235U	^237Np	^238Pu
^242Pu capture	PFR ^240Pu, ^241Pu	^242Pu	^243Am
^241Am capture	Joyo ^241Am, ^243Am PFR ^240Pu, ^241Pu, ^241Am	^241Am	^242mAm
^243Am capture	Joyo ^243Am PFR ^242Pu, ^243Am	^243Am	^244Cm
^244Cm capture	Joyo ^243Am, ^244Cm	^244Cm	^245Cm
^245Cm capture	PFR ^244Pu, ^243Am	^245Cm	^246Cm
^246Cm capture	PFR ^244Pu, ^244Cm, ^246Cm, ^248Cm	^246Cm	^247Cm

Table 3. Average of C/E-1 values and the chi-square values of the ICSBEP benchmark calculations.

	C/E-1				χ2
	J40	B71	B80	J5	J40	B71	B80	J5
All	−0.016%	0.055%	−0.054%	−0.019%	5.419	4.962	3.915	4.029
HEU	0.023%	0.030%	0.097%	0.195%	5.148	5.331	4.576	4.627
IEU	−0.375%	−0.201%	0.038%	0.054%	3.894	1.814	0.854	1.051
LEU	−0.058%	−0.020%	0.054%	0.069%	4.307	3.190	3.000	3.607
MOX	−0.010%	−0.089%	−0.053%	−0.051%	0.579	0.445	0.900	0.968
Pu	0.610%	0.578%	0.090%	0.006%	11.101	11.127	6.237	5.726
U233	−0.550%	−0.242%	−0.457%	−0.304%	4.021	3.691	4.125	4.098

Figure 1. C/E values of criticalities of uranium-fueled light water-moderated system.

K. Tada JENDL-5 Benchmarking for Fission Reactor Applications

Table 4. The δk/k values of uranium-fueled light-water-moderated system when each nuclide is changed from JENDL-5 to JENDL-4.0.

	LCT02–01	LCT02–05	LCT26–01	LCT48–03	LCT48–04	LCT79–02
All	−0.243%	−0.407%	−0.253%	−0.009%	−0.057%	−0.194%
H in H2O	−0.286%	−0.475%	−0.326%	−0.122%	−0.168%	−0.326%
O-16	0.245%	0.151%	0.223%	0.223%	0.153%	0.215%
U-235	−0.098%	−0.109%	−0.139%	0.186%	0.153%	0.051%
U-238	−0.057%	−0.047%	0.008%	−0.158%	−0.160%	−0.143%
Total	−0.196%	−0.480%	−0.235%	0.130%	−0.021%	−0.203%

Figure 2. C/E values of criticalities of gadolinium-loaded thermal systems (LCT005).

K. Tada JENDL-5 Benchmarking for Fission Reactor Applications

Figure 3. C/E values of criticalities of MOX-fueled light-water-moderated system.

K. Tada JENDL-5 Benchmarking for Fission Reactor Applications

Table 5. The δk/k values of MOX-fueled light-water-moderated system when each nuclide is changed from JENDL-5 to JENDL-4.0.

	MCT03–01	MCT03–06	MCT04–10	MCT05–01	MCT05–07	MCT09–05
All	−0.388%	0.032%	0.371%	−0.198%	−0.371%	0.441%
H in H2O	−0.655%	−0.295%	−0.044%	−0.465%	−0.660%	0.001%
O-16	0.213%	0.188%	0.142%	0.193%	0.177%	0.179%
U-235	0.026%	−0.040%	−0.014%	−0.028%	0.028%	−0.003%
U-238	−0.068%	−0.023%	−0.038%	−0.086%	0.008%	−0.041%
Pu-239	0.099%	0.129%	0.248%	0.170%	0.186%	0.371%
Total	−0.484%	−0.170%	0.046%	−0.386%	−0.447%	0.136%

Figure 4. Sensitivity of ¹H scattering cross section in each benchmark case and inelastic scattering cross section of H in H₂O.

K. Tada JENDL-5 Benchmarking for Fission Reactor Applications

Figure 5. C/E values of criticalities of low enriched uranium-fueled solution systems.

K. Tada JENDL-5 Benchmarking for Fission Reactor Applications

Figure 6. C/E values of criticalities of high enriched uranium-fueled solution systems.

K. Tada JENDL-5 Benchmarking for Fission Reactor Applications

Table 6. The δk/k values of LST20 and LST21 when each nuclide is changed from JENDL-5 to JENDL-4.0.

	LST20–01	LST20–02	LST20–03	LST20–04	LST21–01	LST21–02	LST21–03	LST21–04
All	0.124%	0.113%	0.103%	0.094%	0.149%	0.134%	0.127%	0.117%
H in H2O	0.142%	0.131%	0.109%	0.075%	0.166%	0.152%	0.136%	0.105%
O-16	0.168%	0.156%	0.142%	0.139%	0.151%	0.153%	0.144%	0.138%
U-235	−0.142%	−0.118%	−0.105%	−0.085%	−0.147%	−0.126%	−0.095%	−0.093%
U-238	−0.022%	−0.034%	−0.033%	−0.022%	−0.025%	−0.030%	−0.023%	−0.019%
Total	0.147%	0.136%	0.113%	0.106%	0.145%	0.149%	0.163%	0.131%

Figure 7. C/E values of criticalities of low enriched plutonium-fueled solution systems.

K. Tada JENDL-5 Benchmarking for Fission Reactor Applications

Figure 8. C/E values of criticalities of VHTRC.

K. Tada JENDL-5 Benchmarking for Fission Reactor Applications.

Figure 9. Calculated criticalities for each control rod position of HTTR.

K. Tada JENDL-5 Benchmarking for Fission Reactor Applications

Table 7. The calculated criticality and critical control positions of HTTR.

Nuclear data library	Critical control rod position [mm]	Calculated effective multiplication factors	Calculation -Measurement [mm]
J40	1849	1.0000 ± 0.0001	74
B71	1839	0.9999 ± 0.0001	64
B80	1767	1.0000 ± 0.0001	−8
J50	1787	1.0000 ± 0.0001	12
Measurement	1775 ± 5	Not applicable	Not applicable

Figure 10. C/E values of criticalities of small-sized fast systems.

K. Tada JENDL-5 Benchmarking for Fission Reactor Applications

Table 8. The δk/k values of the Big Ten result (IEU-MET-FAST-007-1) when each nuclide is changed from JENDL-5 to JENDL-4.0 or ENDF/B-VIII.0.

	J5 → J40	J5 → B80
All	−0.279%	0.447%
U-235	−0.167%	0.235%
U-238	−0.116%	0.203%

Figure 11. C/E values of criticalities of middle- and large-sized fast systems.

K. Tada JENDL-5 Benchmarking for Fission Reactor Applications

Figure 12. C/E values of sodium-void reactivity worths of ZPPR-9.

K. Tada JENDL-5 Benchmarking for Fission Reactor Applications

Figure 13. C/E values of sodium-void reactivity worths of BFS.

K. Tada JENDL-5 Benchmarking for Fission Reactor Applications

Figure 14. C/E values of sodium-void reactivity worth of an intermediate system.

K. Tada JENDL-5 Benchmarking for Fission Reactor Applications

Figure 15. C/E values of control rod worths of ZPPR-10A.

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Figure 16. C/E values of Doppler reactivity worths of ZPPR-9 and SEFOR.

K. Tada JENDL-5 Benchmarking for Fission Reactor Applications

Figure 17. C/E values of reaction rate distributions of ZPPR-10A.

K. Tada JENDL-5 Benchmarking for Fission Reactor Applications

Figure 18. C/E values of spectrum indices C28/F49 of ZPPR-10A.

K. Tada JENDL-5 Benchmarking for Fission Reactor Applications

Figure 19. C/E values of spectrum indices F42/F49 of BFS.

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Figure 20. C/E values of spectrum indices F64/F49 of BFS.

K. Tada JENDL-5 Benchmarking for Fission Reactor Applications

Figure 21. C/E values of lead-void reactivity worths of three fast systems.

K. Tada JENDL-5 Benchmarking for Fission Reactor Applications

Figure 22. C/E values of isomeric ratio of ²⁴¹Am capture reaction for MA sample irradiation tests in Joyo-MK-II and PFR.

K. Tada JENDL-5 Benchmarking for Fission Reactor Applications

Figure 23. C/E values related to capture cross-sections of ²⁴¹Am, ²⁴³Am, and ²⁴⁴Cm for the MA sample irradiation tests in Joyo-MK-II.

K. Tada JENDL-5 Benchmarking for Fission Reactor Applications

Figure 24. C/E values related to capture cross-sections of ²³⁷Np, ²⁴²Pu, and ²⁴¹Am for the MA sample irradiation tests in PFR.

K. Tada JENDL-5 Benchmarking for Fission Reactor Applications

Figure 25. C/E values related to capture cross-sections of ²⁴³Am, ²⁴⁵Cm, and ²⁴⁶Cm for the MA sample irradiation tests in PFR.

K. Tada JENDL-5 Benchmarking for Fission Reactor Applications